ML20058F742
| ML20058F742 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/16/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058F740 | List: |
| References | |
| NUDOCS 9312080266 | |
| Download: ML20058F742 (3) | |
Text
.-
e# "W, c
- 1
- ( ) *"
E UNITED STATES i h' s,4 /p!
NUCLEAR REGULATORY COMMISSION g
wAssincton, o.c. rosss.cooi SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 147 AND 125 TO FACILITY OPERATING l
LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTICCITYELECTRICCOMPAOY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated July 19, 1993, and supplemented by letter dated August 5, 1993, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit Nos. I and j
2, Technical Specifications (TS). The requested changes would delete i
instrument 9, Boric Acid Tank Solution Level, from Tables 3.3-11 and 4.3-11 and the associated Action 3, for Salem Units 1 & 2.
2.0 EVALUATION The Boric Acid Storage Tanks (BAST) are part of the boration subsystem of the Chemical and Volume Control System (CVCS).
The BASTS supply concentrated boric acid solution to control the boron concentration in the Reactor Coolant System (RCS).
Currently, Technical Specification 3.3.3.7 requires the accident monitoring system instrumentation in Tables 3.3-11 and 4.3-11-to be available for operators to assess and monitor plant conditions following an.
accident. During a Design Basis Accident (DBA) or transient the boration system is not assumed to be operable to mitigate the consequences of the event.
In the event of a malfunction to the CVCS which causes boron dilution, the response is for the operator to close the appropriate valves in the reactor make-up system. The boration subsystem is not assumed to mitigate this event. The BAST level instrumentation is not installed for use in detection or indication of significant degradation of the RCS in the control room.
931EKMSO266 931116 PDR ADDCK 05000272 P
e l
.' Regulatory Guide (RG) 1.97 defines / classifies instrumentation as Type A through E depending on the plant variable they monitor and Category I through III depending upon the importance of the variable monitored. All RG 1.97, Type A instruments and Category I, non-type A instruments, in accordance with the unit's RG 1.97 Safety Evaluation Report, are required to be.in the Post Accident Monitoring (PAM) section of the technical specifications.
Category c
I, non-Type A, instrumentation is required to assist the operators in i
minimizing the consequences of accidents and reducing public risk.
The BAST-q level instrumentation is not classified as Type A or Category I and therefore j
is not required to be in the PAM section of the technical specifications.
In addition. NUREG-1431, Standard Westinghouse Technical Specifications specifies PAMTS variables to include all plant-specific variables classified either as Type A or Category I, non-type A.
The operability of the BAST is required by the Reactivity section of the technical specifications. The boron concentration, minimum contained' volume, 1
and temperature are verified to ensure the BAST operability. Therefore, i
elimination of the BAST instrumentation in the PAM section of the technical j
specifications will not affect the operability of the BAST.
The staff concludes that the proposed changes are consistent with current regulatory requirements. Therefore, the staff concludes that the proposed changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of-a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types,- of any effluents that may be released-offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a i
proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (58 FR.
46240). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
i I
y q
w-p-
3 i
- l
-)
i
5.0 CONCLUSION
2 i
The Commission has concluded, based on the' considerations discussed above,.
I that:
(1) there is reasonable assurance that the health and safety of the L public will not be endangered by operation in the prol osed manner, (2) such activities will be conducted in compliance with the Ctimission's regulations, I
and (3) the issuance of the amendments'will not be inimical to'the common-l defense and security or to the health and safety of the public.
Principal Contributor:
J. Zimmerman l
Date: November 16, 1993 i
I 1
r i
i b
!'l
.