IR 05000338/1987041

Insp Repts 50-338/87-41 & 50-339/87-41 on 871214-18.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp & Testing of Pumps & Valves & Closing of Open Items

ML20195H661
Person / Time
Site:	North Anna
Issue date:	01/06/1988
From:	Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20195H650	List: IR 05000338/1987041 ML20195H646
References
50-338-87-41, 50-339-87-41, NUDOCS 8801200304
Download: ML20195H661 (6)

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UNITED STATES h'@Qtou ;o NUCLEAR REGULATORY COMMISSION

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3 REGION 11

_101 MARIETTA STREET, j

• t ATLANTA, CEORGI A 30323 .

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Report Nos.: 50-338/S7-41 and 50-339/87-41 Licensee: Virginia Electric and Power Company Richmond, VA 23261

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Docket Nos.: 50-338 and.50-339 License Nos.: NPF-4 and NPF-7 Facility Name: North Anna 1 and 2 Inspection Conducted: pecember14-1, 487 Inspector: yt -

j A /T') M ,t / _ h afif N. E of4 s A- Jate/ Signed Approved by: _ .

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J. '.plake,SectionChief Date Signed Ma er/~als and Processes Section D vision of Reactor Safety SUMMARY Scope: This routine, unannounced inspection was in the areas of inservice inspection and. testing of pumps and valves; closing of open items. Also attended the ACRS Joint Subcommittee Meeting on Metal Components / Thermal Hydraulic affects on Steam Generator Integrity.

4: Results: No violations or deviations were identified.

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REPORT DETAILS Persons Contacted ,

Licensee Employees

• L. Bowling, Jr., Assistant Station Manager C. L. Conner, Senior Engineering Technician

• R. F. Driscoll, Manager Quality Assurance

*G. Harkness, Licensing Coordinator

• E. W. Harrell, Station Manager

• G. E. Kane, Assistant Station Manager J. Leberstien, Licensing Engineering

• P. S. Naughton, Engineering Supervisor Inservice Inspection (ISI)

Other licensee employees contacted included QC/QA inspectors, engineers, technicians, and office personne NRC Resident Inspectors J. Caldwell, Senior Resident Inspector L. King, Resident Inspector

• Attended exit interview Exit Interview ,

The inspection scope and findings were summarized on December 18, 1987,

-with those ' persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection findings' listed belo , 339/87-41-01 Open Unresolved Item (URI) Maximum Limiting Stroke Time on IWV Valves (paragraph 4)

i" 338/87-41-02 Open Inspector Followup (IFI) - High Ampere Values on Inside Recirculation Spray Pump B (paragraph 4)

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338/87-41-03 Open IFI - Documentation of Pump and Valve Testing Commitments (paragraph 4)

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Dissenting comments were not received from the license Proprietary information is not contained in this repor i

• Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio .

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2 Inservice Testing of Pumps and Valves - Units 1 and 2 (73756)

Review of Inservice Testing Program Implementation Selected aspects of the licensees implementation of inservice testing (IST) requirements for pumps and valves were reviewed to <erify compliance with regulatory requirements and licensee commitments. ~ The applicable code for IST, as identified through 4.0.5 of the Technical Specifications and 10 CFR 50.55(a)(g) is ASME Section XI, (Subsection IWV, (74S75) for valves and Subsection IWP, 1980 Edition for pumps). The inspector discussed the scheduling, performance, and documentation of pump / valve testing with cognizant on-site personnel. The IST program is documented to procedure, ISI-2.0, 2/27/87 ASME XI IWP/IWV Program. This procedure specifies the responsibilities and surveillance requiremer.ts for pumps and valves including post maintenance testing as applicable. Specifically, pumps and valves included in this program are identified in tne North Anna Power Station Equipment Classification Manual. In addition, to the above, the inspector reviewed the following procedures from VEPCO's ISI Manual for technical conten ISI-10 4/30/87 ASME Section XI Class 1 Valve Visual Examination Program 15I- /21/86 ISI Visual Examination, VT-2 151-12 4/16/87 ASME Section XI Pressure Testing Program In &ddition, the inspector reviewed the documentation of previously

performed pump /ve.ive performance tests (PT) for Units 1 and 2 to determine accuracy, completeness and Code compliance. The pts reviewed were as follows:

Valves Unit Test N Type System Procedure Frequency

! 2SI 112 2 Check Low Head 2P1-138 Refueling Injection

*TVBD1008 "A" 1 Globe "A" S/G Blowdown IPT-21 months

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Inside Con Isolation MOV100B "B" 1 Globe Aux. feedwater 1PT-213.14 3 months j

Supply to "B" S/G

. *MOV1289A "A" 1 Gate Chemical Volume IPT-21 Refueling ( and Control l

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(cont'd) Valves Unit Test r No. ' Type System Procedure Frequency

• MOV2867C 2 Boron Injection 2PT-138 Refueling tank to Cold Leg

• M0V2869B "A" 2 Gate High Head Safety 2PT-21 Cold Shutdown Injection to Cold Leg M0V2867A "B" 2 Gate High Head Safety 2PT-21 months'

Injection Inlet

• Valves requiring periodic leakage testin Pumps

.Inside Recire. Spray Pump A No. I 1PT-64.1A 2/27/87; 6/16/87; 10/3/87 Inside Recirc. Spray Pump B

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No. 1 1PT-64.1B 1/18/87; 3/7/87; 6/16/87 Steam Driven Auxiliary No. 1 1PT-7 /13/87; 2/13/87; Feedwater Pump 4/13/87 Quench Spray System "A" No. 2 2PT-63.1A 1/2/87; 4/2/87; 7/1/87 Subsystem i Residual Heat Removal and No. 2 2PT-7 /16/87 h Valve Test Low Head Safety Injection No. 1 IPT-57.1A 1/3/87; 4/3/87; 7/3/87 Pump Within these areas, the inspector made the following observations: Limiting stroke time for the above valves was not commensurate with the capabilities of the valves tested. Instead, limiting times of full stroke time, in the applicable performance procedures, were related to the particular system response time specified by the station's TS. To illustrate this point, the inspector cited two examples:

Limiting Full Valve Stroke Time Stroke Time T.V. BD-100B 58 seconds 6.1 to 9.7 seconds MOV-FW-100B 60 seconds 29.6 to 30.5 seconds

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The NRC inspector disagreed with the licensee's approach to limiting parameters stating that the staff has' taken 'the - position that limiting values of full stroke time is required to be based en

reasonable engineering judgement of valve operability, not minimum system requirement Moreover, the inspector stated that this position was based on the staff's interpretation of Subsection IWV as a component-oriented code, and as such maximum limiting stroke times should apply speci_fically to valve operability and not minimum system response requirements. The licensee responded by stating that this matter is currently being addressed for the Surry Nuclear Station and a similar resolution was contemplated for North Anna. This matter was identified as an unresolved item pending review of the licensee's resolution. Unresolved Item 338, 339/87-41-01, Maximum Limiting Stroke Time on IWV valves, With regards to Inside ' Recirculation Spray Pump B, the inspector

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noted that one of the three test records reviewed showed that an ampere value of 325A was recorded on March 7,1987. This value was considerably higher than that recorded on an earlier and later test, Date Test Results '

January 18, 1987 120 amps March 7, 1987 325 amps June 16, 1987 100 amps At the time of this inspection, the licensee could not explain the marked increase in the ampere value nor could he produce any objective evidence to show that the incident was investigated by technical personne Therefore, the inspector indicated that an inspector followup item (IFI) would ba identified'in order to permit more time for further investigation into this matte IFI 338/87-41-02, High Ampere Values on Inside Recirculation Spray Pump "B" Certain phases of maintenance work performed on inside recirculation spray pumps A and B (pumps), was observed by the NRC resident inspectors and documented in report 338, 339/87-36. As stated under paragraph 7 of the subject report, back in 1981 the licensee  ;

committed to perform a hydraulic test on the pumps following major 1 maintenanc Following completion of major maintenance work during this outage, the resident inspectors learned that the licensee has ,

. requested the Commission to grant relief from the code required l hydraulic test and as an alternate the licensee proposed to run the ,

pumps dry, to verify operabilit Following discussions between the licensee Headquarters and Region II, the Commission determined that the dry test in this case, was not sufficient to establish operability and the pumps would

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s therefore have to be hydraulically teste In view' of these

- circumstances, the inspector requested that the licensee conduct a -

records search and . determine what other, i f any, commitments'have been made'to the Commission in the area of interes Also, the inspector requested that in the case where other similar commitments were found to exist, they should be included in the pump and valve program manual for North Anna 1 and 2. This item was identified as IFI .338, 339/87-41-03, Documentation of Pump and Valve Testing Commitment '

Within the areas inspected there were no deviations or violations identifie . Inspector Followup Items (92701)

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(Closed) IFI 338, 339/87-35-01, Revise Procedure PT-61.4 to Delineate Corrective Action Requirements The subiect procedure was revised to include past procedure deviations and to specify what action is to be taken if leakage was detected in a valve undergoing testing. The revision was approved on October 28, 198 .. ACRS Joint Subcommittee Meeting on Steam Generator Integrity

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On Dicember 15, 1987, the inspector attended the subject meeting as a repre sentative of Region I Both VEPC0 and Westinghouse (W),

participated in the presentation which focused on the technical aspects of the North Anna, steam generator tube failure. VEPC0 provided a synopsis of the events which led to the tube rupture, including operator action (s)

7.id lessons learned. This was followed by a W presentation which was of a technical nature, focusing on results of the failure analysis, explanation of the failu.e mechanism including the source of the stress loads that contributed to the tube ruptur Other topics of the presentation included steam generator criteria and recommendations applicable to North Anna and other h' plants having Series-51 steam generator .

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