IR 05000280/1977030

Insp Repts 50-280/77-30 & 50-281/77-30 on 771004-07. Noncompliance Noted:Improper Badging of Security Badges. Details Withheld (Ref 10CFR2.790)

ML20150B604
Person / Time
Site:	Surry
Issue date:	11/09/1977
From:	Rogers R, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20150B578	List: IR 05000280/1977030 ML20150B575 ML20150B579 ML20150B589
References
50-280-77-30, 50-281-77-30, NUDOCS 7811010428
Download: ML20150B604 (8)

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Report Nos.: 50-280/77-30 and 50-281/77-30 Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Licensee; Virginia Electric and Power Company P. O. Box 26666

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Richmond, Virginia 23261 Facility Name: 'Surry Units 1 and 2 Inspection at: Surry Power Station, Surry, Virginia Inspection conducted: October 4-7, 1977 Inspectors: R. F. Rogers, III H. L. Whitener Reviewed by: [. pa w # [77 R. C. Lewis, Chief- Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary '

Inspection on October 4-7, 1977: (Report Nos. 50-280/77-30 and 50-281/77-30)

Areas Inspected: Routine, unannounced inspection of piping support and restraint surveillance program; followup of pre.iously identified open and unresolved items; review of IE circulars, Unit 1 Cycle 4 startup report and security badging practices. The insp2ction involved 50  ;

inspector-hours on site by two NRC inspector Results: Of the five. areas inspected, no items of noncompliance or deviations were identified in four areas; one apparent item of noncompliance (Infraction - Improper Security Badging - Details III) was identified in

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'RIl Rpt. Nos. 50-280/77-30 and 50-281/77-30 I-l DETAILS'I Prepared by: . O II!II!77 R. F. Rogers, 271, Reactor Inspector ~ Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: October 4-7, 1977 Reviewed by: [ *d . '

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/h 7 R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclea Support Branch Persons Contacted

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• B. R. Sylvia, Director Nuclear Operations

• T. L. Baucom, Station Manager

• W. L. Stewart, Superintendent, Station Operations

• L. Wilson, Operating Supervisor

• E. P Dewandel, Administrative Assistant

• A. Johnson, Supervisor, Engineering Services

• D. S. Taylor, Supervisor, Mechanical Maintenance R. E. Nicholls, Supervisor, Electrical Maintenance

• F. L. Rentz, Quality Assurance Engineer

• N. Midkiff, Health Physics Supervisor

• E. Johnson, Jr., Security Operation Supervisor

• Denotes those present at the Exit Intervie . Licensee Action on Previous Inspection Findings

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Unresolved Items (Closed)(76-10/2): The inspector reviewed this item concerning lack of a communication procedure as required by' Regulatory Guide 1.33,

" Quality Assurance Program Requirements." The licensee has written and approved Administrative Procedure 53, " Communications Procedure,"

dated July 8, 1977, which the inspector reviewed. This item is considered close . - -Unresolved Items No aew unresolved 11tems were identifie s

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RII Rpt. .Nos.-50-280/77-30'

and 50-281/77-30 1-2 Exit' Interview The inspector met with licensee representatives (denoted in paragraph 1) at the' conclusion-of the inspection on October 7, 1977. -The inspector' summarized the scope and findings of the inspection. The licensee made the-following statements with regards to the findings discussed: Made two commitments' relative to the snubber surveillance progra (1) Insure operability of all-Unit 1 snubbers prior to the ,

return of that unit to power following the next scheduled outar '(2) Visially inspect snubbers on both units in accordance with.T.S. 4.17.C. The next inspection will be performed within 6 months of the date of completion of the functional testing program. This inspection will utilize a revised visual inspection procedur . IE Circular Followup The inspector examined licensee procedures and interviewed licensee representatives.to verify that corrective action, if warranted, had been taken with respect to IE Circulars 77-10, 77-11, and 77-1 None of,the circulars required a response and the inspector had no .!

further: question No items of noncompliance or deviations were identifie . .0utstanding Item Followup IE Report 50-280/76-16 and 50-281/76-16 discussed the need to leak check and repair certain safety injection accumulator check valves. The Unit 2 valves (2-SI-145 and 147) were repaired during.the September refueling outage. The inspector reviewed Maintenance Report S2-012882 dated October 4, 1977, which documented the repair. This item is close 'IE Report 50-280/77-12 and 50-281/77-12 discussed a concern over MMP-C-G-001, " Corrective Maintenance Procedure for Valves-in. General," and its use. The. concern was that the procedure might.be used for' evolutions ,o complex that review by'the >

l Nucleer' Safety Committee:would be desirable. The licensee agreed to audit some of.the completed procedures and make

changes'if required., The inspector reviewed the 75-77 committee

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minutes dated August 10, 1977, and verified that this audit had;been completed' . 'This. item is close ,

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RII Rpt. Nos. 50-280/77-30

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and 50-281/77-30 I-3

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No items of noncompliatce or deviations were identifie . Review of Startup Physics Test Report for Unit 1 ,

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VEP-FRD-26, "Surry Unit 1 Cycle 4 Startup Physics Test keport," was reviewed in the Regional Office. The activities and analyses reported were inspected earlier and were discussed in IE Reports 77-4 and 77- This report supports the conclusions reached earlie .'

No items of noncompliance or deviations were identified.

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RII Rpt. Nos. 50-280/77-30 and 50-281/77-30 11-1 DETAILS II Prepared by: W H.' h Whitener, Reactor Inspector W //

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l Nuclear Support Section No. 1 i Reactor Operations and Nuclear l Support Branch Dates of Inspection: tober 4-7, 1977 Reviewed by: [//,f ~ #/ 7 D." Martin,' Chief / Dgte Nuclear Support Section ho. 1 Reactor Operations and Nuclear Support Branch Persons Contacted

• B. R. Sylvia, Director, Nuclear Operations (Corporate)

• T. L. Baucom, Station Manager

• D. S. Taylor, Supervisor, Mechanical Maintenance L. A. Johnson, Supervisor, Engineering Services

• D. A. Christian, Performance Engineer

• H. L. Eubanks, Mechanical Foreman E. W. Shorter, Mechanic

• denotes those present at exit interview Licensee Action on Previous Inspection Findings This area was not in the scope of this detai . Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviation One unresolved item disclosed during the inspection in discussed in paragraph 7 of this repor . Exit Interview At the conclusion of the inspection an exit interview was held with Mr. T. L. Baucom and members of his staff on October 7, 197 Attendees at this interview are denoted in paragraph The inspector reviewed the areas of inspection, discussed the unresolved item and confirmed commitments with licensee management as delineated in paragraphs 5, 6 and 7 of this repor __ __

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RII Rpt. Nos. 50-280/77-30 and 50-281/77-30 II-2 Pipe Supports And Restraints Selected quality assurance, surveillance and maintenance procedures were reviewed to determine that the licensee has established and implemented an inspection program for hydraulic snubbers and piping supports which incorporates and meets the Technical Specification requirements. Procedures examined during this inspection incluoed the Quality Assurance Program Topical Report (VEP-1-3A), the Nuclear Power Station Quality Assurance Manual (NPSQAM), and Periodic Test and Maintenance procedures as follows:

VEP-1-3A, Paragraph 17.2.5, (3/1/77): Instructions, Procedures and Drawings VEP-1-3A, Paragraph 17.2.10 (3/1/77): Inspection VEP-1-3A, Paragraph 17.2.11 (3/1/77): Test Control VEP-1-3A, Paragraph 17.2.16 (3/1/77): Corrective Action NPSQAM - Section 5.5.8.12 (Revision 10): Periodic Test Procedures NPSQAM - Section 10.5 (Revision 2): Inspection Procedure NPSQAM - Section 11.5.3 (Revision 4): Periodic Test Program NPSQAM - Section 16 (Revision 4): Corrective Action PT 39 (9/30/77): Suppressor Inspection PT 39.1 (3/2/77): 31 Day Snubber Inspection MMP-P-HSS-010 (9/20/77): Preventive Maintenance For Hydraulic Snubbers MMP-P-HSS-020 (9/14/77): Preventive Maintenance For Hydraulic Snubbers The inspector concluded that the licensee has established a program and procedures for inspecting, testing and maintaining hydraulic snubbers consistent with Technical Specification requirement Implementation of the program was verified by review of visual inspection results performed prior to the 1977 refueling outage and functional test results performed during that outag _

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J RII Rpt. Nos. 50-280/77-30 and 50-281/77-30 II-3 Review of procedures for visual inspection of the snubbers, PT 39 and PT 39.1, showed that these procedures lacked adequate specific step by step instructions, acceptance criteria and data requirement The licensee agreed to expand the requirements of these procedures to delineate specific items to be inspected, specific acceptance criteria and specific quantitative "as found-as left" data requirement The inspector identified this matter as a commitment to be completed prior to using PT 39 and 39.1 for a future visual inspection. The inspector will review the rev',ed procedures during a future inspectio . Test Results Review The inspector reviewed the test results of functional testing of 51 hydraulic snubbers from Unit 2 on the ITT Grinnell Shock and Sway Suppressor Tester, Model #543 Of the snubbers tested, 100%

failed to meet the lock up velocity or bleed rate acceptance criteria of 6 in/ min. - 30 in/ min and 2 in/ min - 10 in/ min respectively, established by VEPC0 Engineering in conjunction with vendor and Stone and Webster recommendation The licensee made adjustments and repairs as necessary and tested each snubber to an acceptance criteria 8 1 2 in/ min lock up velocity and 4 i 1 in/ min bleed rate. The inspector had no further questions on Unit 2 snubber Because of the failure rate observed on the Unit 2 snubbers, the inspectors asked for a licensee commitment to test Unit 1 snubbers up to and including 5 inch cylinder bore. Testing of accessible snubbers was initiated immediately by the license The licensee has further committed to testing the inaccessible snubbers at a major outage. The date when this commitment will be implemented is a current subject of discussion between VEPCO and NRC managemen . Snubber Support Maintenance The inspector reviewed corrective maintenance performed on the I-beam supports for two hydraulic snubbers, 2-WAPD-HSS-10 and 11, located on a main feedwater line at the containment operating level. These snubber pistons were found to be in a fully retracted position at cold conditions. The licensee had obtained corrected dimensions for the I-beam supports verbally from Stone and Webster (S&W) based on their evaluation of the thermal properties of the feedwater piping. Documentation confirming these dimensions had not arrived on site at the conclusion of this inspectio The inspector discussed the possibility of overstress in the feedwater line due te the solid condition of the snubbers and obtained the

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RII Rpt. Nos. 50-280/77-30 and 50-281/77-30 II-4 licensee's commitment to verify that no adverse stress condition had existed as a result of the previous snubber and I-beam configuratio At the exit interview the inspector identified the matters requiring further licensee action as unresolved item 77-30-01 as follows:

1) The licensee will verify prior to heat-up of Unit II that no adverse pipe stress condition occurred as a result of snubbers 2-WAPD-HSS 10 and 11 which were found in a solid condition during the refueling outag ) The licensee will obtain documentation confirming the corrected dimensions of the snubber I-beams support The inspector stated that the above areas will be reviewed during a future inspection.

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