INTRODUCTION TO PVGS LICENSING REQUIREMENTS Flashcards
TERMINAL OBJECTIVE:
1 Under all plant operating conditions, describe the PVGS Licensing Requirements in
accordance with Station and Federal documents.
ANSWER ALL CARDS
1.1 Describe what is meant by the term “Code of Federal Regulations”.
The Code of Federal Regulations defines the federal laws governing nuclear power.
1.2 Describe what is meant by the term “The Operating License”.
The “Operating License” gives us permission from the NRC to operate Palo Verde.
Just like an automobile, a license is required to operate a nuclear reactor. The NRC will issue a
license for a reactor when it has reasonable assurance that the public health and safety will be
adequately protected during operation of that reactor. When all requirements of 10 CFR 50.57
(Issuance of Operating License) are met, NRC will issues a license. Each license discusses the
plants compliance with the law and any limitations imposed upon operations.
1.3 Describe what is meant by the term “Final Safety Analysis Report”.
When the company applied for its operating licenses, it also was required to submit a number of
other documents with its application. One of these was the Final Safety Analysis Report (FSAR).
Referencing 50.34(b)…
“The final safety analysis report shall include information that describes the facility, presents
the design bases and the limits of its operation, and presents a safety analysis of the
structures, systems, and components and of the facility as a whole…”
1.4 Describe what is meant by the term “Technical Specifications”.
• Safety limits, Limiting Safety System Settings, and Limiting Control Settings.
The purpose of the Technical Specifications is to:
1. Define safety limits for plant operation,
2. Place time limits on allowed degraded conditions,
3. Place mandatory surveillance requirements on equipment,
4. Define design features of the plant,
5. Designate administrative controls related to plant operations and surveillance requirements.
1.5 Describe the “Definition” section in Technical Specifications.
This section contains the Definitions which will define key terms so that a uniform interpretation of
the Technical Specifications may be achieved.
Many of the terms that are found in this section are applicable throughout the nuclear industry.
1.6 Determine the MODE of Operation.
1.7 State the Safety Limits and describe the bases behind these limits.
2.1.1 Reactor Core SLs
2.1.1.1 In MODES 1 and 2, Departure from Nucleate Boiling Ratio (DNBR) shall be
maintained at ≥ 1.34.
2.1.1.2 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained <
5080 °F (decreasing by 58 °F per 10,000 MWD/MTU for burnup and adjusting
for burnable poisons per CENPD-382-P-A).
2.1.2 Reactor Coolant System (RCS) Pressure SL
In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained at ≤ 2750 psia.
“Safety limits for nuclear reactors are limits upon important process variables that are
found to be necessary to reasonably protect the integrity of certain physical barriers
that guard against the uncontrolled release of radioactivity. If any safety limit is
exceeded, the reactor must be shutdown. The licensee shall notify the Commission,
review the matter, and record the results of the review, including the cause of the
condition and the basis for corrective action taken to preclude reoccurrence.
Operation must not be resumed until authorized by the Commission.”
1.8 State what actions are required (1 hour or less) upon a Safety Limit violation.
If either of the Reactor Core SLs are violated, restore compliance and be in MODE 3 within 1 hour.
If the RCS pressure SL is violated:
• In MODE 1 or 2
o Restore compliance and be in MODE 3 within 1 hour.
• In MODE 3, 4, or 5
o restore compliance within 5 minutes.
With either SL, within 1 hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72
1.9 Describe the Limiting Conditions for Operations section of Technical Specifications.
“Limiting conditions for operation are the lowest functional capability or performance levels of
equipment required for safe operation of the facility. When a limiting condition for operation of a
nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action
permitted by the technical specifications until the condition can be met.”
1.10 Describe the Surveillance Requirements section of Technical Specifications.
Concerning Limiting Conditions for Operations, paragraph 50.36(c)(3) states…
“Surveillance requirements are requirements relating to test, calibration, or inspection
to assure that the necessary quality of systems and components is maintained, that
facility operation will be within the safety limits, and that the limiting conditions of
operation will be met.”
1.11 Describe the Design Features section of Technical Specifications.
Design features are defined in 10CFR 50.36 in paragraph (c)(4) as,
“Design features to be included are those features of the facility such as material of
construction and geometric arrangements, which, if altered or modified, would have a
significant effect on safety and are not covered in categories described in paragraphs
(c)(1)(2), and (3) of this section (of CFR 50).”
In Technical Specifications, section 4.0, design features are specified. The following are included:
4.1 Site
4.2 Reactor Core
4.3 Fuel Storage
1.12 Describe the Administrative Controls section of Technical Specifications
Administrative controls are defined in 10CFR 50.36 in paragraph (c)(5) as,
“Administrative controls are the provisions relating to organization and management,
procedures, record keeping, review and audit, and reporting necessary to assure
operation of the facility in a safe manner.”
1.13 Describe the concept of Risk Informed Completion Times.
The Risk Managed Technical Specifications (RMTS) allow licensees to quantitatively evaluate the
risk associated with the plant configuration to establish extensions of the existing CTs associated
with TS Required Actions. Risk impact is evaluated in terms of Core Damage Frequency (CDF)
and Large Early Release Frequency (LERF).
The calculated Risk Informed Completion Time (RICT) may vary depending on the extent of cause
of the degradation/non-conformance and will consider the effect of other Structures, Systems and
Components (SSCs) that are not functional and plant conditions impacting nuclear safety. The
RICT may credit some proceduralized compensatory measures modeled in the Probabilistic Risk
Assessment (PRA) and may credit other configuration-specific administrative controls taken to
manage risk.
1.14 Describe the two books that are used with the Technical Specifications.
Technical Specification Basis Document
The Actions that are required in Technical Specifications for not meeting an LCO are explained in
the basis document. If a question arises on how to complete an action or if an action is even
necessary the Basis document should have the answer.
Technical Requirements Manual
The Technical Requirements Manual (TRM) is an administrative document used for Palo Verde
specific requirements. The Technical Specifications are more CE generic. If a change is required in
the TRM a 50.59 review is required and the change is made. If a change to Tech Specs is required
a request has to go through the NRC and is a very involved process.
