ML20213E486
| ML20213E486 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/28/1983 |
| From: | Hulman L Office of Nuclear Reactor Regulation |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0611, CON-WNP-611 NUDOCS 8308080605 | |
| Download: ML20213E486 (3) | |
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AEB R/F JUL e8 1983 FAkstulewicz TQuay Plant File docket !!o.:
50-397 MEf'ORAfiDull FOR: Cecil Thomas, Chief Standardization and Special Projects Granch Division of Licensing FR0ll:
L. G. Hulman, Chief Accident Evaluation Cranch Division of Systens Integration
SUBJECT:
PROOF AND REVIEW 0F TECHil! CAL SPECIFICATICfl FOR WASHIflGT0flfluCLEAR - UNIT 2.
Per your request of July 1, 1983, we have reviewed the prooosed technical specifications for the WNP-2 plant. He have identified four itens which are either nissing or inconsistent with the present staff safety evaluation report.
These are:
- 1) fio specification of the naxinun anount of containnent bypass leakage as prescribed by SEP, Section 15.3.1.1.
(Specification 3.6.1.2)
- 2) Refueling pool water depth should specify 23 feet and not 22 feet.
This is necessary to validate staff ossumptions for the fuel handling accident as prescribed by Regulatory Guide 1.25.
(Specifications 3/4.9.8 and 3/4.9.9) 3)
The total ECCS leak rate from all cenponents should not exceed 1 gallon per nicute to be within the SER loss-of-coolant accident evaluation.
The present specification permits leak rates of I gallon per ninute per conponent.
(Specification 3.6.1.2)
- 4) There is presently no specification to centrol the temperature of the control roon during the energency node. We require a technical specification controlling tenperature in the control rcen during the energency node. We suggest that the applicant consider the following wording for Sp(cification 4.7.2.
"At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control rogn air temperature is less than er equal to 85 F."
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Cecil Thcr.as This is necessary to assure a ccnfortable working environnent for the operators and to assure equipnent survivability under nornal and accident conditions.
Pending correction of the items identified above, we can accept these technical specifications for WNP Unit 2.
As requested, enclosed is a list of specifications that are in AEB's area of responsibility.
This review was perforned by F. Akstulewicz (X24993).
~0riginni signed by:
L. G. Eul:an L. G. Ilu1 man, Chief Accident Evaluatinn Gracch Division of Systens Integration
Enclosure:
As stated cc:
R. flattson D. t'uller
- 0. Parr R. Auluck R. Capra
- See Previous Sheet for Concurrence OSI:AEBa OSI:AEB*
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Enclosure Technical Specifications, Bases and Definitions Reviewed by the Accident Evaluation Branch for WNP-2 I.
Definitions 1.9 Dose-equivalent I-131 1.10 E Average Disintegration Energy 1.17 Identified Leakage 1.31 Primary Containment Integrity 1.38 Secondary Containment Integrity 1.40 Site Boundary 1.49 Ventilation Exhaust Treatment System II. Limiting Condition of Operation / Surveillance Requirements 3/4.3.7 Radiation monitoring - CR Intakes 3/4.3.7.8 Chlorine Detection System 3/4.4.3.2 Operational Leakage (RC system) 3/4.4.5 Specific Activity - Reactor Coolant System i
3/4.4.7 Reactor Coolant System - Main Steam Line Isolation Valves 3/4.6.12 Containment Systems - Primary Containment Leakage 3/4.6.1.4 Containment Systems - MSIV Leakage Control Sy. stem 3/4.6.5.1 Containment Systems - Secondary Containment Integrity 3/4.6.5.3 Containment Systems - Standby Gas Treatment System 3/4.7.2 Plant Systems - Control Room Emergency Filtration System 3/4.9.4 Refueling Operations - Decay Time 3/4.9.7 Refueling Operations - Spent Fuel Storage Pool 3/4.9.8 Refueling Operations - Water Level - Reactor Vessel 3/4.9.9 Refueling Operations - Water Level - Spent Fuel Storage Pool III.
Bases for Limiting Conditions of Operation and Surveillance Requirements.
Bases for all LC0/SR's identified in Section II above.
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