ML20077L729
| ML20077L729 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/27/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077L727 | List: |
| References | |
| NUDOCS 9501110495 | |
| Download: ML20077L729 (2) | |
Text
{{#Wiki_filter:' uru h UNITED STATES [4 B NUCLEAR REGULATORY COMMISSION E f WASHINGTON, D.C. 2006M001 i
- g... * *,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N05. 163 AND 144 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND OPR-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
1.0 INTRODUCTION
By letter dated September 29, 1994, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit Nos. I and 2, Technical Specifications (TS). The requested changes would change the surveillance interval for performing an air or smoke flow test through each containment spray header from 5 to 10 years. 2.0 EVALUATION The spray nozzles and piping in the Containment Spray System are fabricated from stainless steel. The spray systems are currently tested on a 5-year interval to confirm the absence of blockage that could potentially impact the required flow rates following a loss-of-coolant accident. NURE-1366, " Improvements to Technical Specifications Surveillance Requb ements," dated December 1992, evaluated the testing of spray nozzles in pressurized water reactors' containment spray systems with stainless steel piping. The conclusion drawn from this evaluation was that the corrosion of stainless steel is negligible during the extended surveillance interval. Therefore, since the spray systems are maintained dry and there are no other postulated mechanisms that could cause blockage, it was concluded that the surveillance interval could be ir.:reased from 5 to 10 years without any reduction in the plant safety. Moreover, the licensee examined the results of the last two surveillance tests and noted that there were no problems that would have resulted in nozzle blockage. The proposed reduced testing of the spray systems' nozzle remains adequate to ensure operability of the nozzles to mitigate the consequences of a Design Basis Accident. Based on all of the above, the staff finds the proposed changes to be acceptable. 9501110495 941227 ^ PDR ADDC' 05000272 P PDR
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 surveillance requirement. 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 60385). 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.
5.0 CONCLUSION
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 Contributor: L. 01shan Date: December 27, 1994
fS Pubhc Servce Electnc and Gas Canpany Joseph J. Hagan Pubhc Sennte Electnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 SEP 2 91994 m, r... ,, -, o,.. - NLR-N94159 LCR 94-29 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: LICENSE AMENDMENT APPLICATION REVISION OF CONTAINMENT SPRAY SYSTEM SURVEILLANCE FREQUENCY SALEM GENERATING STATION UNIT NOS. 1 and 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 This letter submits an application for amendment to Appendix A of Facility Operating Licenses DPR-70 and DPR-75 for the Salem Generating Station Unit Nos. I and 2, respectively, and is being filed in accordance with 10CFR50.90. Pursuant to the requirements of 10CFR50.91(b) (1), a copy of this request for amendment has been sent to the State of New Jersey. The proposed Technical Specification change contained herein represents a change to Section 4.6.2.1 and implements a recommended line item improvement from Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation." The proposed change revises the surveillance interval for performing an air or smoke flow test through each containment spray header from once every five years to once every ten years. It should be noted that similar changes were approved by the NRC Staff for Surry Power Station Unit Nos. 1 and 2 in an SER dated May 20, 1994. The proposed change has been evaluated in accordance with 10CFR50. 91 (a) (1), using the criteria in 10CFR50.92(c), and it has been determined that this request involves no significant hazards considerations. A description of the requested amendment, supporting information and analyses for the change, and the basis for a no significant hazards consideration determination are provided in Attachment 1. The Technical Specification pages affected by the proposed change are provided in Attachment 2 and 3, with pen and ink changes, for Salem Units 1 and 2, respectively. Upon NRC approval of this proposed change, PSE&G requests that the t 9410G70T47 940929 h PDR ADDCK 05000272 P PDR \\ \\
SEP 2 91994 Document Control Desk
- NLR-N94159 amendment be made effective on the date of
- issuance, but implemented within sixty days to provide sufficient time for associated administrative activities.
Should you have any questions regarding this request, please contact us. Sincerely, Affidavit Attachments (3) C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. S. Marschall (SO9) USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 J
REF: NLR-N94159 LCR 94-29 STATE OF NEW JERSEY ) )SS. COUNTY OF SALEM ) J. J. Hagan, being duly sworn according to law, deposes and says: I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief. v Subscribed and Sworn to before me this / day of ? C;Im /JiAm 1994 / 111 bt4[/ t ClLOM 7 0/ KIMBERLY JO BROWN NOTARY PUBilC Of NEW J u, r,,,:,,;,,, r.. . u.:,,,ulSEY My Commission expires on ""WmvJ Vyyy
ATTACHMENT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS LICENSE AMENDMENT APPLICATION REVISION OF CONTAINMENT SPRAY SYSTEM SURVEILLANCE FREQUENCY SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND D"R-75 NLR-N94159 DOCKET NOS. 50-272 and 50-311 LCR 94-29 I. DESCRIPTION OF THE PROPOSED CHANGE This amendment revises Surveillance Requirement 4.6.2.1 by requiring a Containment Spray System header flow test every ten (10) years instead of every five (5) years to confirm that the spray nozzles are unobstructed. II. REASONS FOR THE CHANGE Through this submittal, PSE&G is requesting implementation of the NRC's recommendation regarding the extension of the surveillance interval for performing flow tests through each spray header and verifying that each spray nozzle is unobstructed. The proposed change to the Technical Specifications is consistent with the guidance of Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation" and incorporates the recommendation of NUREG
- 1366,
" Improvements to Technical Specifications Surveillance Requirements." The proposed change is further supported by the associated reduction in radiation exposure to plant personnel and the i elimination of an unnecessary burden on plant staff. III. JUSTIFICATION FOR CHANGE i Technical Specification 4.6.2.1 requires the Containment Spray System to be demonstrated operable at least once every five years by performing an air or smoke flow test through each spray header and verifying that each spray nozzle is unobstructed. The test only verifies that there is flow and i does not provide quantitative data on flow rates through the nozzles. Page 1 of 3
p-Y ATTACHMENT 1 NLR-N94159 LCR 94-29 t As noted by the NRC in NUREG-1366 and. GL 93-05, the NRC re*riewed industry data for problems involving the containment spray system uncovered by means of this testing. The problems found in other facilities occurred during construction or were the result of coatings applied'to.the carbon steel piping. The Salem Unit 1 and Unit 2 Containment Spray Systems. utilizes stainlema steel piping and does not use coating materials such as sodium silicate, the cause of problems in containment spray systems using carbon steel, as noted in GL 93-05, Item 8.1. A review of the previous two (2) Containment Spray nozzle surveillance tests performed on either Salem Unit 1 or Unit 2, indicates there were no problems which would have resulted in nozzle blockage. The proposed change is therefore compatible with Salem Unit 1 and Unit 2 plant operating experience. IV. DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION PSE&G has, pursuant to 10CFR50.92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration. We have determined.that operation of Salem Generating Station Unit 1 and Unit 2, in accordance with the proposed changes:- 1. Does not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed change does not affect the assumptions, design parameters or results of UFSAR accidents analyzed. The proposed change does not involve,a hardware change, a. change to the operation of any system or component, or a 1 change to an existing structure. The proposed change leads to a reduction in radiation exposure to plant personnel and the reduction of an unnecessary burden on. plant staff. The Containment. Spray System header and nozzles are fabricated from corrosion resistant stainless steel and are maintained dry. Operating experience demonstrates that the proposed increase in the Containment Spray surveillance test interval would not affect operability of the system. Testing the Containment Spray System header and nozzles at.the proposed increased i surveillance interval does not increase the probability or consequences of an accident previously evaluated. Page 2 of 3
i ATTACEMENT 1 NLR-N94159 LCR 94-29 2. Does not create the possibility of a new or different kind of accident from any previously evaluated. r The proposed change does not modify equipment, affect the system design basis or operability. This change does not alter parameters utilized in the analyzed accident scenarios. The Containment spray System piping and nozzles are fabricated from corrosion resistant stainless steel. The proposed change in surveillance frequency is consistent-with the guidance provided in GL 93-05. Testing the Containment Spray System header and nozzles at the proposed increased surveillance interval does not create the possibility of a new or different kind of accident from those previously evaluated. 3. Does not involve a significant reduction in a margin of safety. The proposed change only involves a decrease in surveillance frequency and does not alter the performance of the surveillance itself. System equipment and operation remains unchanged. Operability and reliability is still maintained by periodic testing. . Testing the Containment Spray System header and nozzles at the proposed increased surveillance interval does not involve a significant reduction in the margins of safety. V. CONCLUSIONS Based on the above, PSE&G has determined that the proposed change does not involve a significant hazards consideration. Page 3 of 3
P ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION REVISION OF CONTAINMENT SPRAY SYSTEN SURVEILLANCE FREQUENCY SALEM GENERATING STATION UNIT 1 FACILITY OPER) PING LICENSE DPR-70 NLR-N94159 DOCKET NO. 50-272 LCR 94-29 The following Technical Specification for Facility Operating License No. DPR-70 is affected by this License Amendment Request: Technical Soecification Page 4.6.2.1.c 3/4 6-9 i ) s 9+1OO7&tSO 940929 PDR ADDCK 05000272 P PDR
[ ATTACKMENT 3 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES i LICENSE AMENDMENT APPLICATION REVISION OF CONTAINMENT SPRAY SYSTEM SURVEILLANCE FREQUENCY SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE DPR-75 NLR-N94159 DOCKET NO. 50-311 LCR 94-29 The following Technical Specification for Facility Operating License No. DPR-75 is affected by this License Amendment Request: Technical Specification Page 4.6.2.1.d 3/4 6-10 3 B =}}