ML19093A451
| ML19093A451 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/04/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Moseley N NRC/IE, NRC/RGN-II |
| References | |
| IR 1977002 | |
| Download: ML19093A451 (12) | |
Text
{{#Wiki_filter:., VIRGINIA ELECTRIC .A.ND POWER COMP.A.NY RICHMOND, VIRGINIA. 23261 March 4, 1977
~~d Mr. Norman c. Moseley, Director Serial No. 081/022577 Office of Inspection and Enforcement PO&M/TAP/dgt U.S. Nuclear Regulatory Commission Region II - Suite 818 Docket 230 Peachtree Street, Northwest Atlanta, Georgia 30303 DPR-37
Dear Mr. Moseley:
This is in response to your letter of February 25, 1977, in reference to the inspection conducted at Surry Power Station on January 25 through January 28, 1977 and reported in inspection reports IE 50-280/77-2 and 50-2 81 /77-2. e We have reviewed the subject inspection reports and have determined that no proprietary information is contained therein. Accordingly, the Virginia Electric and Power Company interposes no objection to these inspection reports being made a matter of public disclosure. Very truly yours, a-. /) ). ~fie, 1: .*.( _;, t
- c. M. St~llings ;
Vice President-Power Supply and Production Operations
~p.R REGv, _ UNITED STATES c,\; -,>.
0 NUCLEAR REGULATORY COMMISSION 5~~~., ~1 rJ> ., ~ REGION II 230 PEACHTREE STREET, N.W. SUITE 818
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ATLANTA, GEORGIA 30303 {')*~ .....
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In Rep!y Refer To:
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0~ f£5 2 5 1917 IE:II:RFR 50-280/77-2 50-281/77-2 Virginia Electric and Power Company Attn: Mr. W. L. Proffitt Senior Vice President, Power P. 0. Box 26666 Richmond, Virginia 23261 Gentlemen: This refers to the inspection conducted by Mr. R. F. Rogers of this office on January 25-28, 1977, of activities authorized by NRC Oper-ating License Nos. DPR-32 and DPR-37 for the Surry Power Station facilities, and to the discussion of our findings held with Mr. T. L. Baucom at the conclusion of the inspection. Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of selective examination of procedures and representative records, interviews with personnel, and observations by the inspector. Within the scope of this inspection, no items of noncompliance were disclosed. We have examined actions you have taken with regard to previously reported unresolved items. These are identified in Section IV of the summary of the enclosed report. In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office requesting that such information be withheld from public disclos~re. If no proprietary information is identified, a written statement to that effect should be submitted. If an application is submitted, it must fully identify the bases for which information is claimed to be proprietary. The application should be prepared so that information sought to be withheld is incorporated in a separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement,
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- Virginia Electric and Power Company should be submitted to us within 20 days. If we are not contacted as specified, the enclosed report and this letter may then be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to discuss them with you. Very truly yours,
~_s-- -~~~)--"L~
F. J. Long, Chief Reactor Operations and Nuclear Support Branch
Enclosure:
IE Inspection Report Nos. 50-280/77-2 and 50-281/77-2 cc w/encl: T. L. Baucom, Manager. Surry Power Station
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 818 ATLANTA, GEORGIA 30303 IE Inspection Report Nos. 50-280/77-2 and 50-281/77-2 Licensee: Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name: Surry Power Station Docket Nos. : 50-280 and 50-281 License Nos. : DPR-32 and DPR-37 Category: C/C Location: Surry, Virginia Type of License: PWR (W), 2441 Mwt Type of Inspection: Routine, Unannounced Dates of Inspection: January 25-28, 1977 Dates of Previous Inspection: January 4-7, 1977 Principal Inspector: R. F. Rogers, Reactor Inspector Reactor Project Section No. 2 Reactor Operations and Nuclear Support Branch Accompanying Inspectors: None ~ Principal Inspector: (2 .t, _.. 4- -z,/1, 3 /,-, R. F. Rogers, R ~ Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Reviewed by: £, C, ~ z/z-st-/77 R. C. Lewis :ciiw Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2
SUMMARY
OF FINDINGS I. Enforcement Items None II. Licensee Action on Previously Identified Enforcement Matters Not inspected. III. New Unresolved Items None IV. Status of Previously Reported Unresolved Items 75-19/17-3 Repair of Electrical Cable Penetrations Through Fire Walls (Surry 1 and 2) The penetrations have been repaired and accepted by e site QA personnel. This item is closed. (Details, paragraph 2) 75-19/17-5 Revision of Firefighting Procedures (Surry 1 and 2) All required procedures have been written. This item is considered closed. (Details, paragraph 2) 76-1/1 Nuclear Design Check Test Procedure (Surry 1 and 2) Licensee procedures have been revised to include acceptance criteria for physics tests conducted. This item is closed. (Details, paragraph 4) 76-3/3 Revision of NPSQAM (Surry 1 and 2) A revised NPSQAM section on temporary changes still conflicts with Technical Specification requirements. This item remains open. (Details, paragraph 5) 76-5/2 NPSQAM Applicability List (Surry 1 and 2) A review of the NPSQAM applicability list indicates that safety-related systems are now included. This item is closed. (Details, paragraph 6)
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 76-10/2 Calibration of Instrumentation in Safety-Related Systems (Surry 1 and 2) The scope and administration of the licensee's program for periodic instrument calibration is still insufficient in some areas. This item remains open. (Details, paragraph 7) 76-10/3 Outside Recirculation Spray System Pump Performance (Surry 1 and 2) A Technical Specification change has been submitted by the site (13-76) to have shutoff head be the method of measuring pump performance. This item remains open. (Details, paragraph 8) 76-11/1 SYSNSOC Reviews (Surry 1 and 2) Reviews of Technical Specification infractions, reportable occurrences, and system nuclear safety and operating committee minutes have been completed. This item is closed. (Details, paragraph 9) 76-15/1 Site Settlement Surveillance (Surry 1 and 2) The evaluation of the significance of survey data taken in January 1977 has not been completed. This item remains open. (Details, paragraph 10) 76-16/1 Internal Reporting of Occurrences Documentation that corporate personnel were notified of four events was reviewed. This item is closed. (Details, paragraph 11) 76-16/2 Internal Reporting Requirements Internal reporting requirements delineated in the NPSQAM are still not consistent with Technical Specification 6.2.A. This item remains open. (Details, paragraph 12) 76-16/3 System Safety Committee Reviews System Nuclear Safety and Operating Committee reviews have been completed for ten reportable occurrences. This item is closed. (Details, paragraph 13)
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 V. Unusual Occurrences None VI. Other Significant Findings None VII. Management Interview A management interview was held on January 28, 1977, with T. L. Baucom, Station Manager, and members of his staff. The results of the inspection as described in the Summary and Details of this report were discussed. e
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 DETAILS Prepared by: ~-{:" ~ R. F. Rogers,Reatorlnspector l./i.+/11 Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: January 25-28, 1977 Reviewed by: £.c_,~ z/i.-y/77 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
- 1. Personnel Contacted T. L. Baucom - Station Manager W. L. Stewart - Superintendent, Station Operations J. L. Wilson - Operating Supervisor B. A. Boger - Supervisor, Engineering Services E. Dewandel - Administrative Assistant J. A. Hanson, Jr. - Station Fire Marshal D. S. Taylor - Supervisor, Mechanical Maintenance R. E. Nicholls - Supervisor, Electrical Maintenance F. B. Curling - Nuclear Training Coordinator
- 2. Repair of Electrical Cable Penetrations Through Fire Walls (Surry 1 and 2)
Unresolved Item 75-19/17-3 involving the repair of fire stops on cables penetrating fire walls was reviewed. The inspector verified that VEPCO QA had visually inspected the repairs and that they were adequate. - The documentation (EMP-C-FP-23) was complete and the inspector had no further questions. This item is closed.
- 3. Firefighting Procedures (Surry 1 and 2)
Unresolved Item 75-19/17-5 concerning the implementation of firefighting procedures in vital areas was reviewed. Required procedures have been written. This item is closed.
- 4. Nuclear Design Check Test Procedure (Surry 1 and 2)
Unresolved Item 76-1/1 concerning the inclusion of specific acceptance criteria for physics tests was reviewed. Periodic Test (PT) 28.11,
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 "Nuclear Design Check Tests." has been revised to include the specific acceptance criteria for each step of physics tests conducted subsequent to refueling. This item is closed.
- 5. Revision of NPSQAM (Surry 1 and 2)
Unresolved Item 76-3/3 concerns a conflict between Section 5.5.4.1 of the NSPQAM and Technical Specification 6.4.E concerning who can authorize temporary changes to a procedure which does not change the intent of the procedure. The licensee issued a change to the NPSQAM dated November. 30, 1976, but a discrepancy still exists between the Manual and Technical Specifications. This item remains unresolved.
- 6. NPSQAM Applicability List (Surry 1 and 2)
Unresolved Item 76-5/2 concerning the completeness of the safety-related system applicability list in the NPSQAM was reviewed by the inspector. Section 2 of the Manual was revised September 21, 1976, to include those systems required by the definition of safety-related in ANSI N18.7-1972, "Administrative Controls for Nuclear Power Plants." This item is closed.
- 7. Calibration of Instrumentation in Safety-Related Systems (Surry 1 and 2)
Unresolved Item 76-10/2 concerning the calibration of instrumentation in safety-related systems was reviewed. The onsite engineering staff is presently concluding a study of the instrumentation affected. This item will remain open pending implementation of the study results.
- 8. Outside Recirculation Spray System Pump Performance (Surry 1 and 2)
Unresolved Item 76-10/3 concerning the acceptance criteria for recirculation spray pump performance in Periodic.Test (PT) 17.3 was reviewed. A Technical Specification change request (13-76) dated September 8, 1976, was submitted to establish the acceptance of a pump based on its shutoff head only. This is a change to Technical Specification 4.5.B.2 which requires acceptance based on a point on the pump head curve which includes the flow rate variable. This item will remain open pending completion of the change approval process.
- 9. System Nuclear Safety and Operating Committee Reviews (Surry 1 and 2)
Unr_esolved Item 76-11/1 concerning SYS NSOC review of various infractions and reportable occurrences and the documentation of
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 this review was inspected. Committee minutes dated July 28, 1976 and October 29, 1976, covered the items required. This item is closed.
- 10. Site Settlement Surveillance (Surry 1 and 2)
Unresolved Item 76-15/1 concerning the evaluation of the significance of the site settlement data taken in May 1976 was reviewed. The licensee performed another survey which was completed on January 10, 1977. The licensee stated that all results were within acceptance criteria and that the report has been. forwarded to Stone and Webster for evaluation. This item will remain open pending inspector review of the results.
- 11. Internal Reporting of Occurrences (Surry 1 and 2)
Unresolved Item 76-16/1 concerning prompt notification of reportable occurrences to the Director-Nuclear Operations and the Chairman of the System Nuclear Safety and Operating Committee was reviewed. The inspector verified that notifications for the four (4) USREs were made and documented properly. This item is closed.
- 12. Internal Reporting Requirement (Surry 1 and 2)
Unresolved Item 76-16/2 concerning the lack of a requirement in Section 16.5.1.3 of the NSPQAM for prompt notification of corporate officials was reviewed. Technical Specification 6.2.A requires this notification for 30-day reportable occurrences. A licensee representative stated that the change to the NSPQAM had been submit-ted on November 2, 1976. This item will remain open pending implementa-tion of the change.
- 13. System Safety Committee Reviews (Surry 1 and 2)
Unresolved Item 76-16/3 concerning System Nuclear Safety and Opera-ting Committee reviews of reportable occurrences was inspected. The inspector reviewed committee minutes dated July 28, October 29, and December 28, 1976, and noted that the required reviews had been made. This item is closed.
- 14. Flooding of Safety-Related Equipment From Non-Category I' Seismic)
Sources (Surry 1 and 2) The inspector reviewed the status of completion of a design change to prevent the flooding of safety-related equipment sufficient to prevent a safe shutdown of the plant. Design change 74-55, "Flood Control," embodies commitments made to the commission in a December 30, 1974, VEPCO response to an October 31, 1974, NRR request for an
e IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 analysis of the potential for this type of accident at Surry. Design change 74-55 consists of seven appendices which are listed. Appendix A - Circ Water Expansion Joint Shields (12/Unit) Appendix B - Concrete Dikes (4 locations) Appendix C - Circ Water Flood Trips Appendix D - Flood Control - Fire Protection System Appendix E - Flood Control - MISC Controls Appendix F - Flood Control - Additional Controls Appendix G - Additional Alarms The first six appendices have been completed. The remaining Appendix G consists of the installation of level switches in vital areas with remote indication in the control room. This item will remain open pending completion of the design change and inspector review of the final results.
- 15. Pressurizer Level Setpoints (Surry 2)
VEPCO Reportable Occurrence Report No. USRE-S2-76-06, dated May 27, 1976, describes an event relating to high pressurizer level trip setpoints that had drifted in the unconservative direction. The inspector verified that the long term action on changing the setpoint two percent in the conservative direction was performed. The high level trip setpoint was changed from 90% to 88%. The low level engineered safeguards actuation was changed from 7% to 9% on both units. Both changes moved the setpoint in a conservative direction. This item is closed.
- 16. Station Nuclear Safety and Operating Committee Minutes IE Report 50-280/76-11 and 50-281/76-11 discussed the need for improvements in SNSOC meeting minutes. The inspector reviewed recent copies of SNSOC minutes and noted improvements that have been made in accountability and tractability. This item is closed.
- 17. Polar Crane Procedure IE Report 50-280/76-17 and 50-281/76-17 discussed the need for a procedure addressing the operation of the Polar Crane. The inspector reviewed MMP-P-CR-015, "Preventative Maintenance Procedure for cranes and Lifting Equipment" dated January 11, 1977, which references ANSI N45.2.15, USAS B30.2, and OSHA Section 1910.79 requirements.
The inspector had no further questions.
IE Rpt. Nos. 50-280/77-2 and 50-281/77-2 18. Review of Safety Limits, Limiting Safety System Setting, and Limiting Conditions for Operation (Surry 1 and 2) Reactor operations were reviewed in order to ascertain whether Technical Specification requirements for safety limits, limiting safety system settings, and limiting conditions for operation are being adhered too. The examination consisted of direct observation of process instrumentation, consoles, panels, and annunciator boards. The inspector also reviewed records, logs, charts and held discussions with operators on shift. Approximately fifteen (15) parameters which have Technical Specification limiting values were selected at random and checked for conformance to required values. Systems affected included the reactor coolant system, control rod system, turbine system, containment system, safety injection system, spray system, and emergency power system. Within the areas inspected, the inspector had no further questions.}}