ML19093A415

Response to Letter of 09/01/1977 in Reference to Inspection Conducted on 08/18-08/21/1977 and Reported in Inspection Reports IE 05000280/1977023 & 05000281/1977023

ML19093A415
Person / Time
Site:	Surry
Issue date:	09/15/1977
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	O'Reilly J NRC/IE, NRC/RGN-II
References
IR 1977023
Download: ML19093A415 (7)

Text

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VJ:RGINJ:A. ELECTRIC A.ND POWER COMPANY

- RICHMOND, VIRGINIA 23261 September 15, 1977 Mr. James P. O'Reilly, Director Serial No. 392/090177 Office of Inspection and Enforcement PO&M/TAP:dgt U. S. Nuclear Regulatory Commission Docket N ~ ; ~

Region II - Suite 818 230 Peachtree Street, Northwest

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License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37

Dear Mr. O'Reilly:

This is in response to your letter of September 1, 1977, in reference to the inspection conducted at Surry Power Station on August 18-21, 1977, and reported in inspection reports IE~S0-280/77-23 and 50-281/77-23.

We have reviewed your letter and the enclosed inspection reports and have determined that no proprietary information is contained in the reports. Accord-ingly, the Virginia Electric and Power Company interposes no objection to these

~inspections reports being made a matter of public disclosure.

Very truly yours,

~,)!)1. -dk.c~/*~ry C. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. Robert W. Reid

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA, GEORGIA 30303 SEP 1 1977 In Reply Refer To:

RII:FJ 50-280/77-23 50-281/77-23 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. Frank Jape of this office on August 18-21, 1977, of.activities authorized by NRC Operating License Nos. DPR-32 and DPR-37 for the Surry Unit 1 and 2 facilities, and to the discussion of our findings held with Mr. W. L. Stewart 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 examinations 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.

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 (or your contractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must include a full statement of the reasons on the basis of which it is claimed that the information is proprietary, and should be prepared so that proprietary information*identified in the application is contained in a separate part of the document. If we do not hear from you in this regard within the specified period, the report will be placed in the Public Document Room.

Virginia Electric and Power Company Should you have any questions concerning this letter, we will be glad to discuss them with you.

Very truly yours,

---~~ong, C h i o ~

Reactor Operations and Nuclear Support Branch

Enclosure:

RI! Inspection Report Nos.

50-280/77-23 50-281/77-23

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA, GEORGIA 30303 Report Nos.: 50-280/77-23 and 50-281/77-23 Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Licensee: Virginia Electric and Power Company P.O. Box 26666 Richmond, Virginia 23261 Facility Name: Surry Units 1 and 2 Inspection at: Surry Power Station, Surry, Virginia Inspection conducted: August 18-21, 1977 Inspector-in-Charge: F. Jape Accompanying Personnel: None Reviewed by: ~.c.~ 9/1/77 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Inspection Summary Inspection*on July 19-21, 1977 (Report Nos. 50-280/77-19 and 50-281/77-19)

Areas Inspected: Routine, unannounced inspection of plant operations, conduct of maintenance and Quality Assurance activities. The inspection involved 28 inspector-hours on site by one NRC inspector.

Results: Of the three areas inspected, no items of noncompliance or deviations were found.

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- RII Rpt. Nos. 50-280/77-23 and 50-281/77-23 DETAILS Prepared by: ./?.C. j.uA 9/1/77

~ F. Jape, Reactor Inspector Date

~- - Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: August 18-21, 1977 Reviewed by: f!, C. * ~ 9/1/77 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch

1. Persons Contacted T. L. Baucom, Station Manager W. L. Stewart, Superintendent, Station Operations D. S. Taylor, Supervisor Mechanical Maintenance J. L. Wilson, Operating Supervisor T. A. Swanson, Shift Supervisor L.A. Wagner, Shift Supervisor S. R. Burgold, Assistant Shift Supervisor D. R. Sanderson, Assistant Shift Supervisor B. C. Delamorton, Control Room Operator E. O. Harding, Control Room Operator R. L. Trevillian, Jr., Control Room Operator B. Purdy, Auxiliary Operator D. Ramney, Auxiliary Operator C. Crommby, Control Room Operator R. W. Cephas, Quality Assurance Engineer

2. Licensee Action on Previous Inspection Findings Not applicable.

3. Unresolved Items No new unresolved items were identified.

4. Exit Interview An exit management interview was held with w. L. Stewart on August 21, 1977. The scope and findings of the inspection were summarized. ~~~-~-~

The licensee representative had no questions or dissenting comments regarding the inspection.

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- RII Rpt. Nos. 50-280/77-23 5.

and 50-281/77-23 Plant Operations The inspector reviewed plant operations to ascertain conformance with regulatory requirements, technical specifications and adminis-trative procedures. Station logs, such as the Shift Supervisors Log, Control Room Operators Log and the Minimum Equipment Log were reviewed using Administrative Procedure 29, "Conduct of Operations,"

Section 29.1.2 and Technical Specification 6.5 as guidance.

Four shift turnovers from mid shift to day shift were observed.

Two different shift crews were observed due to the rotating shift schedule. The turnovers were conducted as prescribed in Section 29.3.1 of ADM 29. Activities by supervision and operations during the shift were also observed and found to comply with Section 29.3.2 of ADM 29.

The number of personnel available on each shift exceeded the minimum required by Technical Specification 6.1 B.3. Operators were responsive to annunciator alarms and were fully cognizant of plant status.

During the inspection two significant events plus a reactor startup occurred on Unit 1 providing the inspector an opportunity to observe operator and supervisory reaction to these events. The first event involved a dropped control rod and the second was a turbine runback.

The startup occurred after the unit was shutdown to repair the dropped control rod. Unit 2 operated at design power throughout the inspection period. There were no items of noncompliance or deviations identified within the areas inspected.

6. Plant Tour The inspector accompanied plant operators on their routine patrol of the auxiliary building and the outside service areas. Observations were made regarding the general plant housekeeping and cleanliness, ongoing activities, status of operating equipment, security practices and radiation control practices. In general, the housekeeping and cleanliness were found to be satisfactory. The nonradiation areas were found to be less cluttered than areas within the auxiliary building. No problems were observed regarding operating equipment during the tour. Security and radiation control practices were adhered to during the tour.

7. Maintenance The inspector reviewed the records of two recently completed mainte-nance requests. These were overhaul of the containment air compresser

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RII Rpt. Nos. 50-280/77-23 and 50-281/77-23 and repair of valve PCV-2455A. The documentation was found to be in accordance with Section 16, "Corrective Actions," pf the NPSQA manual.

Detailed procedures were utilized for each job. Workmen had signed and dated each step as required, and performed the required post maintenance checkout. Acceptance criteria specified within the procedure were met.

8. Quality Assurance The inspector reviewed activities conducted by Quality Assurance Staff in support of plant operations. The requirement for performing these activities is delineated in Section 4.3.4 of the VEPCO NPSQA Manual. Periodic audits are required to be conducted by the Station staff. Audits are conducted *on an annual schedule, and weekly surveillances are performed on security, radiation protection or operations.

Weekly surveillance reports for the past four weeks were reviewed.

These reports covered security, fire protection, chemistry and radiation protection. A written report was prepared and distributed.

Followup of the findings were completed for inprocess on these reports. The program appeared to be functioning as prescribed.

The file records for the annual audits for the following areas were reviewed:

a. Mechanical Maintenance

b. Operator Training, and

c. Maintenance training.

Followup on deficient audit items was also examined. Implementation of these audit requirements were found to be in agreement with the program *

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