ML20209H705
| ML20209H705 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/16/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209H650 | List: |
| References | |
| GL-83-28, NUDOCS 8702060118 | |
| Download: ML20209H705 (2) | |
Text
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/ o UNITED STATES
[' c '8f ,,g NUCLEAR REGULATORY COMMISSION
- C WASHINGTON D.C.20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LETTER 83-28. ITEM 4.4 IMPPOVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR BAW PLANTS CRYSTAL RIVER NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-302 INTRODUCTION AND
SUMMARY
Generic Letter 83-281 describes intermediate term actions to be taken by licensees \
and applicants to address the generic issues raised as a result of the staff's evaluation of the two ATWS events that occurred at Unit 1 of the Salem Nuclear Power Plant.
Item 4.4 of Generic Letter 83-28 required licensees and applicants to confirm that safety-related maintenance and test procedures are applied to the diverse reactor trip feature provided by interrupting power to the control rods through L the silicon controlled rectifiers (SCRs). In addition, the test procedure should verify that the SCRs have degated, thereby removing power from the control rods {
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and the SCRs shall be included in the surveillance and test requirements sections of the Technical Specifications.
This report is an evaluation of the response submitted by Florida Power Corporation, the licensee for the Crystal River Nuclear Plant, Unit 3, for Item 4.4 of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of this report.
EVALUATION The licensee for the Crystal River Nuclear Plant, Unit 3 responded p to the rqquire-ments of item 4.4 with submittals dated November 4, 1983 , January 16, 1984~,
and July 31, 19844 . The licensee confirmed in these submittals that safety-j related procedures are being used to maintain and test the SCRs. The licensee
, further stated that the procedures used to test the SCRs verify that the SCRs under test have deqated and. opened the power supply to the control rods. The licensee also stated that Technical Specification changes were beino made that l
would include the SCRs in the maintenance and test requirements section of the Technical Specifications. The acceptability of these Technical Specification changes will be reported in the SER for Generic letter 85-10 (Item 4.3 TS -
MPA B-90).
CONCLUSION Based on our review of these responses, we find.the licensee's statements confirm that the SCRs are maintained and tested using safety-related procedures. The testing will confirm the opening of the power supply to the control rods, and Technical Specification changes are being made to include the SCPs in the maintenance and test requirements section o' the Technical Specifications.
These actions meet the requirements of Item 4.4 of Generic Letter 83-28 and are acceptable.
8702060118 870116 PDR ADOCK 05000302 P PDR
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REFERENCES ;
- 1. NPC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, "Pequired Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
- 2. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Response to Generic letter 83-28," November 4, 1983.
- 3. Florida Power Corporation letter to NPC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Technical Specification Change Request No. 111,"
i January 16, 1984 i
4 Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Updated Response to Generic Letter 83-28," July 31, 1984.
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TECHNICAL EVALUATION REPORT CONFORMANCE TO GENERIC LETTER 83-28 ITEM 4.4 ARKANSAS NUCLEAR ONE, UNIT 1 CRYSTAL RIVER UNIT 3 DAVIS-BESSE UNIT 1 OCONEE UNITS 1, 2 AND 3 RANCHO SECO THREE NILE ISLAND UNIT 1 WNP 1
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Published October, 1986 Idaho National Engineering Laboratory EG&G Idaho, Inc.
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Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 .
Under DOE Contract No. DE-AC07-761001570 FIN No. D6001 and 06002
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4 ABSTRACT
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This EG&G Idaho, Inc. report provides a review of the submittals for Babcock & Nilcox (B&W) nuclear plants for conformance to Generic Letter ?
83-28. Item 4.4. The group includes the following plants:
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. Plan Docket Number' TAC Number
- Arkansas Nuclear One, Unit 1 50-313 53952
- Cristal River Unit 3 50-302 53953 s Davis-Besse Unit 1 50-346 53954 l'- Oconee Unit 1 50-269 53955
' 0conee Unit 2
., 5.0-270 53956 50-287 53957
"[0coneeUnit3 Rancho Seco _
50-312 53958
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Three Mile Island Unit 1 50-289 53959 WNP 1 50-460 N/A A 6 6
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FOREWORD This report is provided as part of the program for evaluating licensee / applicant conformance to Generic Letter 83-28 " Required Actions .-
based on Generic Implications of Salem ATWS Events." This work is conducted for the U. S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation. Division of PWR Licensing-A, by EG&G Idaho, Inc.
The U. S. Nuclear Regulatory Commission funded the work under the authorization, B&R 20-19-19-11-3 and 20-19-40-41-3, FIN No. D6001 and D6002.
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CONTENTS ii ABSTRACT .............................................................
iii FOREWORD .............................................................
- 1. INTRODUCTION ....................................................
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- 2. REVIEW REQUIREMENTS ............................................. 2 3
- 3. GROUP REVIEW RESULTS ............................................
REVIEW RESULTS FOR ARKANSAS NUCLEAR ONE, UNIT 1 ................. 4 4.
4 4.1 Evaluation ................................................
4 4.2 Conclusion ................................................
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- 5. REVIEW RESULTS FOR CRYSTAL RIVER UNIT 3 .........................
5.1 Evaluation ................................................ 5p 5
5.2 Conclusion .................................................
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- 6. REVIEW RESULTS FOR DAVIS-BESSE UNIT 1 ...........................
6 6.1 Evaluation ................................................
6 6.2 Conclusion ................................................
- 7. REVIEW RESULTS FOR OCONEE UNITS 1, 2 AND 3 ...................... 7 7
7.1 Evaluation ................................................
7 7.2 Conclusien ................................................
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- 8. REVIEW RESULTS FOR RANCHO SECO ..................................
8 8.1 Evaluation ................................................
8 8.2 Conclusion ................................................
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- 9. REVIEW RESULTS FOR THREE MILE ISLAND UNIT 1 .....................
9 9.1 Evaluation ................................................
9 9.2 Conclusion ................................................
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- 10. REVIEW RESULTS FOR WNP 1 ........................................
10 10.1 Evaluation ................................................
10 10.2 Conclusion ................................................
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- 11. GROUP CONCLUSION .......... ... - -
- 12. REFERENCES ......... ... ..
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CONFORMANCE TO GENERIC LETTER 83-28 ITEM 4.4 ARKANSAS NUCLEAR ONE. UNIT 1 CRYSTAL RIVER UNIT 3 0 AVIS-BESSE UNIT 1 e.
OCONEE UNITS 1, 2 AND 3 RANCHO SECO THREE MILE ISLAND UNIT 1 WNP 1
- 1. INTRODUCTION I
On July 8, 1983, Generic Letter 83-28 was issued by D. G. Eisenhut, Director of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating licenses, and -
holders of construction permits. This letter included required actions based on generic implications of the Salem ATWS events. These requirements have been published in Volume 2 of NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant."2 This report documents the EG&G Idaho, Inc review of the submittals from Arkansas Nuclear One, Unit 1, Crystal River Unit 3 Davis-Besse Unit 1, Oconee Units 1, 2 and 3, Rancho Seco, Three Mile Island Unit 1 and WNP 1 for conformance to Item 4.4 of Generic Letter 83-28. The submittals from the licensees utilized in these evaluations are referenced in Section 12 of this report.
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- 2. REVIEW REQUIREMENTS Item 4.4 (Reactor Trip System Reliability - Improvements in Maintenance and Test Procedures for B&W Plants) requires licensees and applicants with B&W reactors to apply safety-related paintenance and test procedures to the diverse reactor trip feature provided by interrupting power to control rods through the silicon controlled rectifiers (SCRs).
The Item does not require any hardware changes nor additional environmental or seismic qualification of these components, but it does require inclusion of safety related maintenance and test procedures for the SCRs in the appropriate surveillance and test sections of the Technical Specifications.
Responses from the included B&W plants were evaluated against a minimum description of how safety related maintenance and test procedures can be applied to the SCRs in the Control Rod Drive Control System. Each p response should:
- 1. Confirm that the requ).'4 action has been implemented.
- 2. Include a brief description of the safety related procedures used to conduct periodic surveillance, testing and maintenance of the SCR diverse reactor trip feature, that includes degating the SCRs and verifies that they have opened the power supply circuit to the control rod drive holding coils.
- 3. Confirm that Technical Specification changes which include requirements for safety related surveillance and tests of the SCRs to be performed at intervals commensurate with existing test intervals for other safety related portions of the reactor trip system are submitted to the NRC, or verify that these requirements are included in the existing plant Technical Specifications.
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- 3. GROUP REVIEW RESULTS The relevant submittals from each of the B&W reactor plants were reviewed to determine compliance with Item 4.4. First, the submittals from each plant were reviewed to establish that Item 4.4 was specifically addressed. Second, the submittals were evaluated to determine the extent to which each of the B&W plants complies with the staff guidelines for Item 4.4.
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- 4. REVIEW RESULTS FOR ARKANSAS NUCLEAR ONE, UNIT 1 4.1 Evaluation Arkansas Power and Light Company (AP&L), the license for Arkansas Nuclear One, provided their response to Item 4.4 of the Generic Letter in submittals dated November 5, 1983, and April 24, 1985. In the first response, the licensee states that AP&L supports the B&W Owners Group generic guidelines for SCRs, is evaluating those guidelines and will incorporate those guidelines into procedures "as applicable." That response also states that the safety related Reactor Protection System channel functional test provides for monthly testing of the SCRs with the exception of verification of actual degating. Their response of April 24, 1985, states that testing of the SCRs is conducted using safety related test procedures; verification of degating of the SCRs was added to the p procedures and the test procedures now meet the B&W guidelines.
4.2 Conclusion The licensee's submittals tonfirm implementation of Item 4.4 of the Generic Letter: testing of the SCRs is conducted using safety related procedures, verification of degating of the SCRs is included in those procedures, and the procedures comply with the BWOG guidelines for this testing. The staff finds this acceptable.
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S. REVIEW RESULTS FOR CRYSTAL RIVER UNIT 3 S.1 Evaluation Florida Power Corporation (FPC). the licensee for Crystal River Unit 3, provided responses to Item 4.4 of the Generic Letter on November 4, 1983, January 16, 1984, and July 31, 1984. In those responses FPC confirmed implementation of Item 4.4, identified the Crystal River Surveillance and Maintenance procedures and requested an amendment to the Crystal River Technical Specifications to explicitly include SCR operability and SCR degating.
5.2 Conclusion The licensee submittal confirms implementation of Item 4.4 of the -
Generic Letter, complete with verification of SCR degating. The staff finds that this is acceptable.
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- 6. REVIEW RESULTS f 0R DAVIS-BESSE UNIT 1 6.1 Evaluation Toledo Edison, the licensee for Davis-Besse Unit 1, responded to Item 4.4 of the Generic Letter on December 9, 1983, and on July 9, 1985.
The latter response states that Davis-Besse 1 has installed the capability to test the ability of the SCRs to trip the reactor, and that he does intend to apply safety related maintenance and test procedures to the SCRs.
6.2 Conclusion The licensee submittal comfirms implementation of Item 4.4 of the Generic Letter. We have reviewed information describing the testing of the SCR trip feature that is classified as safety related and that includes p verification that the SCRs degate and interrupt power to their holding coils. The staff finds this acceptable.
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- 7. REVIEW RESULTS FOR OCONEE UNITS 1, 2 AND 3 .
- 7.1 Evaluation Duke Power Company, the licensee for Oconee units 1, 2 and 3, responded to Item 4.4 of the Generic Letter on November 4, 1983, and August 9, 1985. In those responses, the licensee concurs with the contents of the B&W Owners Group position. The responses also confirm that surveillance and maintenance of the SCRs will be performed under procedures which comply with all requirements of safety related procedures, and state that the surveillance test will be revised to include adequate documentation of verification that the SCRs have appropriately responded to a RPS signal.
7.2 Conclusion The licensee's response does confirm that the procedures used for maintenance and testing of the SCR trip feature comply with all the requirements of safety related procedures, that tie testing of the SCRs is included in Technical Specifications, and that the testing will verify that the SCRs respond to a trip sign'a1. The staff finds that this is acceptable.
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- 8. REVIEW RESULTS FOR RANCHO SECO 8.1 Evaluation Sacramento Municipal Utility District (SMUD), the licensee for Rancho Seco, provided a response to Item 4.4 of the Generic Letter on November 4, 1983. That response states that SMUD has satisfactorily tested the SCRs using the test procedure prepared by B&W for the B&W Owners Group, and that the SCR test procedure will be incorporated into the monthly Reactor Protection System instrument test procedure. The response did not include the test procedure prepared by B&W, nor did it include a description of the procedure. We have reviewed the BWOG proposed test
- procedure which provides for the verification of degating of the SCRs by noting a decrease in output current of the affected power supply.
8.2 Conclusion The licensee response does confirm that the B&W Owners Group recommended test procedures will be used for testing the SCRs and will be incorporated in the RPS monthly test procedure. The staff finds that this is acceptable.
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- 9. REVIEW RESULTS FOR THREE MILE ISLAND UNIT 1 9.1 Evaluation GPU Nuclear Corporation, the licensee for Three Mile Island Unit 1 (TMI-1), responded to Item 4.4 of the Generic Letter on November 8,1983.
That response states that the SCRs are classified as Nuclear Safety Related at TMI-1, and that, while the trip function of the SCRs was not previously verified, the Reactor Protection System test procedure has been revised to include confirmation of the trip function by verifying a reduction in current from the affected power supply. Administrative Technical Specification changes were submitted to provide explicit inclusion of the SCRs on September 30 and October 9, 1985.
9.2 Conclusion -
The licensee's response does confirm that the SCR trip feature -is safety related and that procedures would be revised to confirm that the SCRs will open the holding coil circuit when degated. Review of the licensee's safety related procedure confirms that his test procedure includes verification of degating of the SCRs. The staff finds this acceptable.
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- 10. REVIEW RESULTS FOR WNP 1 10.1 Evaluation Washington Public Power Supply System, the applicant for WNP 1, responded to Item 4.4 of the Generic Letter on March 30, 1984. The response states that the applicant intends to apply safety related maintenance and test procedures to the SCRs.
10.2 Conclusion The applicant submittal comfirms implementation of Item 4.4 of the Generic Letter. However, the licensee's submittal does not include a description of the procedures used. It is evident that the concern of Item 4.4 of Generic Letter 83-28 will be resolved on an industry-wide basis .?
prior to completion of the technical specifications for WNP-1 and will be resolved for this plant during the review and approval process of its technical specifications. Therefore, the staff considers this Item to be closed for this evaluation.
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, 11. GROUP CONCLUSION The staff concludes that the licensee responses for Item 4.4 of Generic Letter 83-28 are acceptable.
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- 12. REFERENCES
- 1. NRC Letter, D. G. Eisenhut to all licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implicationsof Salem ATWS Events (Generic letter 83-28)," July 8, 1983.
- 2. Generic Implications of ATWS Events at the Salem Nuclear Power Plant NUREG-1000. Volume 1. April 1983; Volume 2, July 1983.
- 3. Arkansas Power and Light Company letter to NRC, J. Ted Enos to D. G. Eisenhut, Director, Division of Licensing, NRC, "86W Owners Group Response to Generic Letter 83-28," November 4, 1983.
- 4. Arkansas Power and light Company letter to NRC, J. R. Marshall to D. G. Eisenhut, Director, Division of Licensing, NRC, " Arkansas Nuclear One Response to Generic Letter 83-28," November 5, 1983.
- 5. Arkansas Power and Light Company letter to NRC, J. Ted Enos to Director of Nuclear Reactor Regulation, NRC, " Response to RFI - Items 4.4 and 4.5.3," April 24, 1985.
- 6. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Response to Generic Letter 83-28," November 4, 1983.
- 7. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Technical Specification Change Request No. 111 "
January 16, 1984.
- 8. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Updated Response to Generic Letter 83-28," July 31, 1984.
- 9. Toledo Edison letter to NRC, R. P. Crouse to Director of Nuclear Reactor Regulation, NRC, December 9, 1983.
- 10. Toledo Edison letter to NRC, Joe Williams to Director of Nuclear Reactor Regulation, NRC, July 9, 1985.
- 11. Duke Power Company letter to NRC, H. B. Tucker to H. R. Denton, Director, Office of Nuclear Reactor Regulation, November 4, 1983.
- 12. Duke Power Company letter to NRC, H. B. Tucker to H. R. Denton, Director, Office of Nuclear Reactor Regulation, August 9, 1985.
- 13. Sacramento Municipal Utility District letter to NRC, R. J. Rodriquez to D. G. Eisenhut, Director, Division of Licensing, NRC, " Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," November 4, 1983.
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- 14. GPU Nuclear Corporation letter to NRC, H. D. Hukill to D. G. Eisenhut, Director Division of Licensing, NRC, " Required Actions Based on Generic Implications of Salem /ATWS Events," November 8, 1983.
- 15. Washington Public Power Supply System letter to NRC, G. C. Sorenson to Director of Nuclear Reactor Regulation, " Nuclear Project No. 1 Response to Generic Letter 83-28, Salem ATWS Event," March 30, 1984.
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