ML19093A446
| ML19093A446 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/26/1977 |
| From: | Long F Virginia Electric & Power Co (VEPCO) |
| To: | Moseley N NRC/IE, NRC/RGN-II |
| References | |
| IR 1977007 | |
| Download: ML19093A446 (10) | |
Text
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VIRGINIA ELECTRI*c AND POWER CoMPANY RICHMOND, VIRGINIA 23261 Mr. Nonnan C. Moseley, Director Serial No. 190/050677 Office of Inspection and Enforcement PO&M/TAP:~dgt U. s. Nuclear Regulatory Commission Docket No. 50-280 Region II - Suite 818 230 Peachtree Street, Northwest License Nos. PR-32 Atlanta, Georgia 30303 DPR-37
Dear Mr. Moseley:
This is in response to your letter of May 6, 1977, in reference to the inspection conducted at Surry Pbwer Station on April 12-15, 1977 and reported in inspection reports IE 50-280/77-7 and 50-281/77-7.
We have reviewed the subject inspection reports and have determined that no proprietary infonnation is contained therein. Accordingly, the e Virginia Electric and Power Company interposes.no objection to these in-spection reports being made a matter of public disclosure.
u~tr; e ul ~~rs, ), .
- M. Stallings esident-Power Su ply roduction Operations cc: Mr. Robert W. Reid
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA, GEORGIA 30303 M~Y 6 W7 Virginia Electric and Power Company Attn: Mr. W. L. Proffitt Senior Vice President, Power P.O. Box 26666
- Richmond, Virginia 23261
/
Gentlemen:
This refers to the inspection conducted by Mr. R. F. Rogers of this office on April 12-15, 1977, of activities authorized by NRC Operating 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 also examined actions you have taken with regard to previously identified enforcement matters and unresolved items. The status of these items is identified in Sections II and 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 RoomL 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 disclosure. If no proprietary information is identified, a written statement to that effect should be submitted. If an application is e
MAY Virginia Electric and Power Company 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 0
- and referenced in the application since*the application will be placed in the Public Document Room. Your application, or written statement, 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, F. J. Long, Chief Reactor Operations and
. Nuclear Support Branch
- e.
Enclosure:
.IE Inspection Report Nos.
50-280/77~7 and 50-281/77-7
.cc w/encl:. T. L. Baucom, Mana~er Surry Power Station e
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA, GEORGIA 30303 IE Inspection Report Nos. 50-280/77-7 and 50-281/77-7 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: April 12-15, 1977 e Dates of Previous Inspection: March 29- April 1, 1977 Principal Inspector: .R. F. Rogers, III, Reactor Inspector Accompanying Inspectors: None Other Accompanying Personnel: None Principal Inspector: 02.C ~ ;*;HI R. F. R o g e r s ~ t o r Inspector s/s'/11 Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Srro1t Branch Reviewed by: * \l1c eA.c-.,e -
~ R ~ s , Chief Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
IE Rpt. Nos. 50-280/77-7 and 50-281/77-7
SUMMARY
OF FINDINGS I. Enforcement Items None II. Licensee Action on Previously Identified Enforcement Matters Infraction IE Inspection Report 50-280/77-1 and 50-281/77-1
,/
Item I. - Implementation of the corrective actions identified in VEPCO's letter of March 9, 1977, were verified and this item is closed. (Details, paragraph 2)
III. New Unresolved Items None IV. Status of Previously Reported Unresolved Items 76-3/3 Revision of NPSQAM (Surry 1 and 2)
A revised NPSQAM section on temporary changes now agrees with Technical Specification requirements. This item is closed. (Details, paragraph 5) 76-16/2 Internal Reporting Requirements (Surry 1 and 2)
Internal reporting requirements delineated in the NPSQAM are now consistent with Technical Specifications. This item is closed. (Details, paragraph 6)
V. Unusual Occurrences
.None VI. Other Significant Findings Licensee's actions in response to a deviation concerning VEPCO management responses to the NRC were inspected. This item is closed. (Details, paragraph 3)
- e IE Rpt. Nos. 50-280/77-7 and 50-281/77-7 VII. Management Interview A management interview was held on April 15, 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 *
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IE Rpt. Nos. 50-280/77-7 and 50-281/77--7 DETAILS Prepared by :_~fl~.~I'.~.__J~~~::.!.:*~*='='=--- S /s/7 /
R. F. Rogers, I , Reactor Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Insp 1977 Reviewed by:__:~~~........~~!IQ'..S.Llr..:!~~~:..._~~~~
~R. wis,
.,/ 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 e J. L.
E. P.
. B. A
- Wilson - Operating Supervisor Dewandel - Administrative Assistant Boger - Supervisor, Engineering Services D. s. Taylor - Supervisor, Mechanical Maintenance R. "E. Nicholls - Supervisor, Electrical Maintenance J. s. Fisher - Station Fire Marshal
- 2. Followup of Previously Identified Enforcement Items - Control Room Documentation (Surry 1 and 2)
An infraction concerning control room documentation was initially identified in Item I.5. of Report 76-14 dated October 21, 1976. A repeat infraction in this area was identified in Item I. of Report 77-1 dated February 16, 1977. The inspector conducted a review on April 13, 1977 to ascertain whether facility operations were now in conformance with Regulatory Requirements, Technical Specifications,
.and Adminstrative Procedures. Shift Logs, Operating Records,
.Jumper Logs, Tag Logs, and Logbook reviews were inspected against the requirements of Administrative Procedure 29, "Conduct of Opera-tions" and Technical Specification 6.4, "Unit Operating Procedures."
The inspector reviewed records to verify that the licensee had implemented corrective action as stated in VEPCO responses dated December 6, 1976 and March 9, 1977. The corrective action appeared to be effective and these items of noncompliance are considered closed.
_..___ .,.__,_,_, ___ .____._=-~---*--*-~* - ~ - ~ *~_...__.._ ___ .*_c *. _. ___ *-****---* .,._ ._,_, .. *-*
IE Rpt. Nos. 50-280/77-7 and 50-281/77-7 3. *Followup of Previously Identified Deviation - Management Responses (Surry 1 and 2)
A deviation concerning inadequate management responses was initially identified in Item VI of Report 77-1 dated February 16, 1977. The inspector verified that the corrective actions discussed in the VEPCO response dated March 9, 1977 had been implemented. A licensee representative stated that communications with the Richmond Office had improved. An on-site followup review of recent VEPCO corres-pondence indicated that this problem area had received attention.
,,,This item is considered closed.
- 4. Reportable Occurrences (Surry 1 and 2)
.a. Inoffice Review The inspector reviewed the following Surry Licensee Event Reports in the Regional Office. Each report was evaluated for completeness, that the item was reported as required by Technical
- Specifications(TS) 6.2 and 6.6, the cause was identified, e corrective action was taken as required by TS 6.2.A and B, and that operating limitations delineated in TS section 2 and 3 were-met. The evaluation of these occurrences and the resulting reports typically involved telephone discussions with licensee representatives to assure that requirements were being satisfied.
The following reports have been received and reviewed:
- Surry 1 USRE-Sl-76-05, dated May 27, 1976 USRE-Sl-76-06, dated May-27, 1976 USRE-Sl-76-07, dated July 29, 1976 USRE-Sl-76-12, dated October 1, 1976 USRE-Sl-76-13, dated October 20, 1976
_USRE-Sl-76-14, dated November 2, 1976 USRE-Sl-76-15, dated November 17, 1976 USRE-Sl-76-16, dated November .17, 1976 USRE-Sl-76-17, dated November.24, 1976 USRE-Sl-76-18, dated December 2, 1976
-RO-Sl-77-01, .dated January 24, 1977
-RO-Sl-77-02, dated February 9, 1977 RO-Sl-77-03, dated February 16, 1977 RO-Sl-77-04, dated February 16, 1977 RO-Sl-77-05, dated February 28, 1977
IE Rpt. Nos. 50-280/77-7 and 50-281/77-7 RO-Sl-77-06, dated March 3, 1977 RO-Sl-77-07, dated March 16, 1977 RO-Sl-77-08, dated March 16, 1977 Ro-Sl-77-09, dated March 18, 1977 Surry 2 USRE-S2-76-05, dated May 27, 1976 USRE-S2-76-07, dated July 7, 1976 USRE-S2-76-09, dated July 13, 1976 USRE-S2-76-11, dated July 21, 1976
./ USRE-S2-76-14, dated November 2, 1976 USRE-S2-76-15, dated November 5, 1976 USRE-S2-76-15 (supplement), dated November 22, 1976 USRE-S2-76-16, dated January 19, 1977 RO-S2-77-0l, dated February 16, 1977 RO-S2-77-02, dated February 28, 1977 RO-S2-77-03, dated March 10, 1977
- VEPCO nomenclature was changed from USRE (Unusual Safety
.Related Event) to RO (Reportable Occurrence) for reportable items subsequent to January 1, 1977.
- b. Onsite Followup Review The inspector reviewed the following selected repor.table occurrences at the station. Events selected were evaluated to assure that the event occurred as described, licensee stated corrective actions were completed, the event was reviewed and evaluated as required, and generic implications were assessed.
Surry 1 USRE-Sl-76-06, dated May 27, 1976 USRE-Sl-76-07, dated July 29, 1976 RO-Sl-77-04, dated February 16, 1977 RO-Sl-77-05, dated February 28, 1977 RO-Sl-77-08, dated March 16, 1977 RO-Sl-77-09, dated March 18, 1977 Surry 2 USRE-S2-76-16, dated, January 19, 1977 RO-S2-77-0l, dated February 16, 1977 RO-S2-77-02, dated February 28, 1977 RO-S2-77-03, dated March 10, 1977
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- e IE Rpt. Nos. 50-280/77-7
--and 50-281/77-7 ;Within paragraphs a. and b. above, the inspector found that the licensee had not yet completed corrective action discussed in USRE-S2-76-16. This report describes the dilution of the Boron Injection Tank (BIT) below specifications due *to leakage of BIT inlet valves MOV-2867A and MOV-2867B. The stroke check described as a long term corrective action remains to be performed. This item will be reviewed on a subsequent inspection.
- 5. Revision of NPSQAM (Surry 1 and 2)
Unresolved Item 76-3/3 discussed a conflict between Section 5.5.4.1,
/'of the NPSQAM and Technical Specification 6.4.E. concerning temporary
-change authorizations. A change to this section dated April 7, 1977 resolved the problem. - This item is closed.
- 6. Internal Reporting Requirements *(surry 1 and 2)
Unresolved Item 76-16/2 discussed the lack of a requirement in Section 16.5.1.3 of the.NPSQAM for prompt notification of corporate officials -of 30-day reportable events. A change to this section e 7.
dated .February 3, 1977 added the requirement. This item is closed.
Plant Tour (Surry 1 and 2)
A plant tour was conducted on both units to verify that monitoring
-equipment was recording as required, equipment was properly tagged, operations personnel were aware of plant conditions, and that plant housekeeping efforts were adequate. IE Inspection Report 76-4, Details III, discussed the need for increased attention in*the housekeeping and cleanliness areas. The inspector noted that improvements had been achieved in cleanliness and that the specific items in Report 76-4 had received attention. The inspector had no further comments.