ML20076K901
| ML20076K901 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/20/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076K897 | List: |
| References | |
| NUDOCS 9411020181 | |
| Download: ML20076K901 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20656 4001
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EAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS 158 AND 139 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 i
1.0 INTRODUCTION
By letter dated February 18, 1994, as supplemented by letter dated April 6, i
1994, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit No. 1, Technical Specifications (TS) and by letter dated March 28, 1994, the licensee submitted a request for changes to the Salem Nuclear Generating Station, Unit No. 2 TSs. The requested changes would replace the main feedwater control (BF-19s) and main feedwater control bypass (BF-40s) valves with the main feedwater stop check (BF-22s) valves for the containment isolation function in the Table 3.6-1 of the Salem Unit 1 TSs.
The amendment also changes the Salem Unit 2 TS by adding a footnote to the 21 - 24 BF22 (main feedwater stop check valves) on Table 3.6-1, " Containment Isolation Valves." This note identifies those containment isolation valves that are not subject to 10 CFR Part 50, Appendix J, Type C leakage testing.
2.0 BACKGROUND
During the initial licensing of Salem, Unit 2, the licensee identified the stop check valves in the main feedwater system for containment isolation purposes.
In addition, Salem, Unit 1 feedwater system is functionally identical to Unit 2 and was also using stop check valves in the main feedwater system for containment isolation purposes.
However, in January 1981, the staff issued Safety Evaluation Report, Supplement 5 (NUREG-0517) that identified a concern with the use of the stop check valves. The main feedwater stop check valves at Salem had local-manual operators.
In the event of an accident, environmental and/or radiological conditions could preclude operator access to the local-manual valve operator.
If the valves could not be accessed to positively close the valves, the stop check valves then function;d as a simple check valve.
General Design Criterion 57 (GDC 57) 9411020181 941020 n
PDR ADOCK 05000272 P
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I requires closed systems that penetrate the containment to have at least one containment isolation valve which shall be either automatic, or locked closed, or capable of remote manual operation.
GDC 57 further states that a simple check valve may not be used as the automatic isolation valve. Therefore, the design did not meet GDC 57.
The licensee, by letter dated August 18, 1981, proposed to install motor operators on the stop check valves with remote-manual operation from the control room or new air / electric valves in the main feedwater system as the means to meet GDC 57.
By letter dated September 30, 1981, the staff accepted the licensee's proposal. Motor operators were installed on all main feedwater stop check valves at both Salem units.
However, the technical specifications were not changed to show the stop check valves as the containment isolation valves for the main feedwater system.
When the issue was raised in the 1990 time period, the licensee re-evaluated the suitability of the stop check valves for containment isolation and concluded that the remote-manual closure feature utilized non-safety related controls in the main control room. Design modifications were made to the control circuits to upgrade them to safety related.
3.0 EVALUATION 3.1 Salem Unit 1 Technical Specification Changes The containment isolation function, as contained in Table 3.6-1 of the TS, is currently provided by the main feedwater flow control valves and main feedwater flow control bypass valves. These valves automatically close on actuation of the Reactor Trip System (safety injection or reactor trip coincident with low T. ) and/or Engineered Safety Features Actuation System.
The proposal to chang,e,the containment isolation function to the main feedwater stop check valves will provide the same function without reliance on an actuation signal.
Positive closure is assured during all accident scenarios through the remote-manual controls in the nm'n control room.
The main feedwater stop check valves (BF-22s) are included in the Inservice Test Program and are also included in the motor operated valve program as requested by Generic Letter 89-10.
By including the valves in these programs, there is reasonable assurance that the valves will be adequately maintained.
Therefore, the staff concludes that the stop check valves, 11 - 14 BF-22, meet the requirements of GDC 57 and finds the proposed changes acceptable.
Administrative changes relocate existing information, ado the word " supply" to the functional description of valve 12CA360, and delete Note 1.
Note 1 is removed since the identified valves (BF-19s and BF-40s) are no longer used for the containment isolation function.
In addition, the # footnote for the 11-14 BF-22s has been added to identify these valves as exempt from Type C leakage testing which is consistent with the Salem Updated Final Safety Analysis Report (UFSAR) Table 6.2-13 list of containment isolation valves.
These changes do not affect the the containment isolation function.
The staff finds these changes acceptable.
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1 3.2 Salem Unit 2 Technical Specification Change The change to the Salem Unit 2 TS adds a footnote to the 21 - 24 BF22 (main feedwater stop check valves) on Table 3.6-1, " Containment Isolation Valves."
This note identifies those containment isolation valves that are not subject to 10 CFR Part 50, Appendix J, Type C leakage testing. This change will eliminate the inconsistency between the Salem, Unit 2 TSs and UFSAR Table 6.2-13 list of containment isolation valves. The staff finds this change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment.
The State official had no comments.
5.0 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 proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 37083). 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.
6.0 CONCLUSION
i The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
J. Stone J. Zimmerman Date: October 20, 1994 I
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