IR 05000280/1978035
| ML18113A895 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/12/1979 |
| From: | Burke D, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18113A894 | List: |
| References | |
| 50-280-78-35, 50-281-78-35, NUDOCS 7903070522 | |
| Download: ML18113A895 (7) | |
Text
Report Nos. :
Docket Nos. :
License Nos. :
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 50-280/78-35 and 50-281/78-35 50-280 and 50-281 DPR-32 and DPR-37 Licensee:
Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name:
Surry Power Station Inspection at:
Surry, Virginia
Inspector:
Inspection Summary Inspector No. 2 Support Branch
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Inspection on December 4-22, 1978 (Report Nos. 50-280/78-35 and 50-281/78-35)
Areas Inspected:
Routine inspection by the resident inspector of plant operations, Licensee Event Reports, IE Circulars, plant organization changes, plant physical protection barriers, and previously identified unresolved and open items. The inspection involved 104 inspector-hours by the NRC resident inspecto Results:
No items of noncompliance or deviations were identified in the six areas inspecte g-?
RII Rpt. No. 50-280/78-35 and 50-281/78-35 I-1
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DETAILS I Prepared by: ::7Ru_ £11~£~
D. J. Burke, Resident Reactor Inspector Reactor Projects Section No. 2 Operations and Nuclear Dates of Reviewed rt Branch
. C. Lewis, 1978 Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted Virginia Electric and Power Company (VEPCO)
T. L. Baucom, Station Manager - 1 W. L. Stewart, Superintendent, Station Operations - 2 J. L. Wilson, Operating Supervisor - 1/2 E. P. Dewandel, Administrative Assistant - 1 T. A. Peebles, Supervisor, Engineering Services - 1 J. W. Patrick, Supervisor, Mechanical Maintenance F. L. Rentz, Resident QC Engineer - 1/2 D. L. Hahn, Engineer - 2 J. Fisher, Fire Marshall - 2 1):171 Date j;rfa?
Date Several Control Room Operators, Shift Supervisors, QC, Engineering, and Records personne /
Denotes those present at the management interview on December 15, 197 /
Denotes those present at the management interview on December 22, 197.
Licensee Action on Previous Inspection Findings Unresolved Items (Closed) Unresolved Item (78-16-08):
Adequacy of Snubber Instal-lation and Identificatio Two snubbers (2-GCB-HSS- 002 and 003)
have been installed on the Unit 2 steam generator blowdown piping; the three existing snubbers on the Unit 1 blowdown piping were
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RII Rpt. No. 50-280/78-35 and 50-28i/78-35 I-2 evaluated by Stone and Webster and the licensee and determined to be adequate (See RII Rpt. Nos. 50-280/78-30 and 50-281/78-30, paragraph 5.e.). In addition, the licensee has submitted to NRR a corrected listing of safety-related suppressors for Technical Specification Tables 4.17-1 and 4.17- (Closed) Unresolved Item (78-16-10):
QA personnel Trainin The licensee has established a training plan for the QA/QC personnel in QA instruction 7.1, and has implemented the program. The training is in accordance with ANSI N18.1, N45.2.6, and N45.2.23. Specific training on snubbers has been conducte (Closed) Unresolved Item (78-16-13):
QA level of involvemen QA/QC overviews of entire evolutions during maintenance are being conducted; recent audit examples included maintenance on several safety-related valves, recirculation spray pump maintenance, and steam generator tube inspections and repair Open Items (Closed) Open Item (78-16-13):
Deviation Report threshhol The licensee has conducted training sessions with all plant employees with regard to the threshhold for initiating Deviation Reports and the mechanisms available for reporting deficiencie The current identification, documentation, and reporting of deficiencies appears appropriat (Closed) Open Item (78-16-14): QA hold points for valve inspection The inspector verified that QA/QC hold points for the inspection of safety-related valves prior to closure (to inspect the internal con-ditions) have been incorporated into the valve maintenance procedures (MMP-C-G-001).
No foreign substances were found during the valve inspections reviewe.
Unresolved Items No new unresolved items were identifie Management Interviews Management interviews were conducted on December 15 and 22, 1978, with the members of station management denoted in paragraph The inspector summarized the scope and findings of the inspections. The submission of annual reports was also discussed. The resident inspector also attended the exit interview of J. L. Skolds, Region II inspector, on December 14, 197.,.,
- RII Rpt. No. 50-280/78-35 and 50-281/78-35 1-3 Review of Reportable Occurrences The inspector 'reviewed the Reportable Occurrence (RO) reports listed below to ascertain that NRC reporting requirements were being met and to determine the appropriateness of corrective action taken and planne Certain Licensee Event Reports were reviewed in greater detail to verify corrective action and determine compliance with the Technical Specifications and other regulatory requirement The review included examination of log books, internal correspondence and records, review of SNSOC meeting minutes, and discussions with various staff member Within the areas inspected, no items of noncompliance or deviations were identifie LER 280/78-31, dated November 6, 1978, concerned drift in the Channel I pressurizer level instrumentation. The leak detected in the bypass equalizing valve was secured and the instrument recali-brated. This item is close LER' s 280/78-32, 78-33, 78-36 and LER 281/78-40, concerned the failure of heat tracing circuits on borated water lines due to boric acid damag Since redundant circuits exist, the temper-atures in the piping served by the affected circuits was maintained as required during the event However, due to the number of failures, the licensee has initiated maintenance efforts to reduce boric acid leakage and engineering studies to consider the instal-lation of more impervious heat tracin The licensee stated that these matters would be noted on subsequent LER's of this natur These LER's are close LER 280/78-40, dated November 29, 1978, concerned the failure to perform the periodic test (PT 22.4) on the emergency diesel generators 1 and 3 during the last refueling outag The inspector verified that the inspection tests were performed and that an administrative memorandum was issued concerning the scheduling of periodic tests to pre,~lude another oversigh This item is close, LER 280/78-42, dated December 12, 1978, concerned the inadvertent temporary isolation of the steam generator blowdown monitor Corrective action appeared adequate. This item is close e *
LER 281/78-28, dated September 1, 1978, addressed operation with the containment partial pressure above TS limit This item is close.)",
- RII Rpt. No. 50-280/78-35 and 50-281/78-35 I-4 LER 281/78-31, dated September 8, 1978, concerned the failure of circulating water valve 200C to a close. This item is close LER 281/78-34, dated October 31, 1978, addressed two inoperable snubbers which were replaced due to mechanical seal damag This item is close LER 281/78-35, dated November 1, 1978, concerned the failure of circulating water valve 202B to close. This item is close LER 281/78-37, dated November 14, 1978, concerned an inoperable steam generator blowdown radiation monitor RM-21 The loose electrical connector was tightened and operation res to re This item is close LER 281/78-39, dated December 12, 1978, concerned the failure of RCS Loop B temperature sensor due to a nearby valve packing lea The leak was within TS limits and the sensor drift corrected. This item is close.
IE Circulars IE Circular 77-15, which concerned fuel oil flow to the emergency diesel generators, was received and reviewed by appropriate licensee personnel, and adequate responsive actions have been taken. This item is close.
The inspector toured the Unit 1 and Unit 2 control rooms and certain plant areas to observe that monitoring equipment and plant instrumen-tation was functioning as required, and that the facility operations were in accordance with the Technical Specification Plant logs and records were also reviewe Within the areas inspected, no items of noncompliance or deviations were identifie Specific areas of inspection included: Review of the Unit 1 Steam Generator "C" leak which led to the shutdown of Unit 1 on December 12, 197 Review of the minor fire on December 22, 1978, in the heat tracing on Boric Acid Transfer Pump "C"; the response of the station fire team was prompt and effectiv Follow-up on alarmed annunciators in the control room The inspector noted that procedures did not exist for alarms H-2 on panel D of both units, which annunciate certain valve pit high water level (Open Item 280/281/78-35-0l).
The licensee stated that the procedures are in preparation, and will,be expedite,...
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RII Rpt. No. 50-280/78-35 and 50-281/78-35 I-5 The alarms are a part of a recent plant modification to control potential flooding of vital areas. The inspector verified that the alarm circuits were operable and that the operators responded to the alarm Review of the charging pump service water (SW) subsystem valve corrossion proble (See LER's 280/78-04 and 280/78-11).
The licensee experienced Unit 1 valve steam failure on December 2 and December 4, 1978; on December 6, the licensee began replacing the remaining non-stainless steel valve stems in Unit 1 with stainless steel stems. The maintenance was completed during the Unit 1 shutdow The inspector verified that the limiting conditions for operations were not exceeded. Follow-up on the Unit 2 valves continue Review of the tests performed in accordance with the November 29, 1978 letter from the Office of Nuclear Reactor Regulation which required the licensee to test the containment personnel airlock doors in accordance with Appendix J to 10 CFR 50 (i.e., six month intervals and after each opening).
The inspector verified that periodic test 16.7. "After Opening Personnel Airlock Leakage Test",
is being performed in accordance with the abov Review of the Control Room Operator and Shift Supervisor Logs for December, 197 Verification of selected safety injection system valves and components for proper position or contro Tour of Unit 1 containment and verification of certain pipe pene-tration seals, snubber installation and steam generator inspection radiation control Verification of control room manning in accordance with TS 6..
Plant Physical Protection The inspector verified the following observations: Gates and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromised or obstructe Personnel were properly identified, searched, authorized, badged, and escorted as necessary for plant access control.
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RII Rpt. No. 50-280/78-35 and 50-281/78-35 I-6 Within the areas inspected, no items of noncompliance or deviations were identifie.
Organization and Administration The inspector verified that the recent staff changes at the site meet the requirments of the Technical Specification and ANSI Nl8. The qualifications of recent appointees T. A. Peebles, Supervisor, Engineering Services, and J. W. Patrick, Supervisor, Mechanical Maintenance, were in accordance with the requirement No items of noncompliance or deviations were disclosed.
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