ML20217M599

Forwards Request for Addl Info Re Third Interval Inservice Testing Program for Pumps & Valves at James a FitzPatrick Nuclear Power Plant Submitted on 971021

ML20217M599
Person / Time
Site:	FitzPatrick
Issue date:	04/30/1998
From:	Williams J NRC (Affiliation Not Assigned)
To:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
TAC-MA0096, TAC-MA96, NUDOCS 9805050059
Download: ML20217M599 (7)

Text

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+A Mr. J:mes Knubel . , April 30, 1998 l Chtf Nuclear Officer . ' l.

Power Authority cf the Stat 3 of r New York +

'123 Main Street White Plains, NYE10601

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SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR '

ADDITIONAL INFORMATION REGARDING THE '

INSERVICE TESTING PROGRAM-

-(TAC NO. MA0096) ,

Dear Mr. Knubel:

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. On October 2.1; 1997, the New York Power Authority submitted th' e Third interval inservice

' Testing Program for Pumps and Valves at the ~ James A4 FitzPatrick Nuclear Power Plant. The NRC staff has determined that additional information, as described in the enclosure, will be required in order to complete its review of this submittal.

Please contact me at (301) 415-1470 if you have any questions on this topic.

~ Sincerely, Original Signed by: ~,

\

Joseph F. Williams, Project Manager Project Directorate 1-1 l' Division of Reactor Projects - 1/11 office of Nuclear Reactor Regulation ,

Docket No. 50-333

Enclosure:

Request for Additional Information cc w/ encl: Seo next page DISTRIBUTION:

53 Gat Me / S. Little - K Dempsey

- PUBLIC J. Williams PDl-1 R/F OGC J. Zwolinski . ACRS S. Bajwa C. Hehl, Region I '

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i DOC'UMENT NAME: G:\FITZWIA0096.RAI y0}

To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attichment/ enclosure "N" = No copy OFFICE PM:PDI-1 //1, l E LA;PDl40 (f l EMEB l D.PDI-1 , ,A l l NAME JWdliameAco1/F Suttle *" SBajwa ADM 044/98 //

DATE O W J/98 OW /98 OWJO98 Official Record Copy

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• A Mr.J mes Knubel April 30, 1998 Chilf Nucletr Officer Power Authority of the Stat 3 of 3 New York 123 Main Street White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE INSERVICE TESTING PROGRAM (TAC NO. MA0096)

Dear Mr. Knub31:

On October 21,1997, the New York Power Authority submitted the Third intervai inservice Testing Program for Pumps and Valves at the James A. FitzPatrick Nuclear Power Plant. The NRC staff has determined that additional information, as described in the enclosure, will be required in order to complete its review of this submittal.

Please contact me at (301) 415-1470 if you have any questions on this topic.

Sincerely, Original Signed by:

Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects -l/ll Office of Nuclear Reactor Regulation l

Docket No. 50-333

Enclosure:

Request for Additional Information cc w/ encl: See next page DISTRIBUTION-Docket File S. Little K. Dempsey 1 PUBLIC J. Williams i PDI-1 R/F OGC i J. Zwolinski ACRS

8. Bajwa C. Hehl, Region 1 DOCUMENT NAME: G:\FITZ\MA0096.RAI l

To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure *E" = Copy with

- citichment/ enclosure ,"N"= No copy OFFICE PM.PDI-1 41,lE LAPDI-10 V l EMEB l D.PDl-1 , ,A l l l NAME JWiNiemeAcc#/ V SUttle ** SBalwa APQ l o4/4/98 4/

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DATE' o4/J/98 o4/ MI6 04/JO98 l l

Official Record Copy l

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1 a ur uq p k UNITED STATES g [ NUCLEAR REGULATORY COMMISSION o & WASHINGTON, D.C. 30015 4001

% + April 30, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York -

123 Main Street .

White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE INSERVICE TESTING PROGRAM (TAC NO. MA0096) ,

Dear Mr. Knubel:

On October 21,1997, the New York Fower Authority submitted the Third Interval inservice Testing Program for Pumps and Valves at the James A. FitzPatrick Nuclear Power Plant. The NRC staff has determined that additional information, as described in the enclosure, will be required in order to complete its review of this submittal.

Please contact me at (301) 415-1470 if you have any questions on this topic.

Sincerely, Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/ll ,

Office of Nuclear Reactor Regulation l I

Docket No. 50-333 i

Enclosure:

Request for Additional Information cc w/ encl: See next page

James Knubel James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc:

Mr. Gerald C. Goldstein Regional Administrator, Region 1 -

Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President New York State Energy, Research,-

Resident inspector's Office and Development Authority U. S. Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington Avenue Extension Lycoming, NY 13093 Albany, NY 12203-6399 Mr. Harry P. Salmon, Jr., V.P. Mr. Richard L Patch, Director Nuclear Operations - Quality Assurance Power Authority of the State Power Autnority of the State of New York of New York 123 Main Street 123 Main Street White Plains, NY 10601 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering Director Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of New York 123 Main Street Mr. James Gagliardo White Plains, NY 10601 Safety Review Committee 708 Castlewood Avenue Supervisor Arlington, TX 76012 Town of Scriba Route 8, Box 382 Mr. ArthurZaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41 President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State - Mr. Paul Eddy of New York New York State Dept. of 123 Main Street Public Service White Plains, NY 10601 3 Empire State Plaza,10th Floor Albany, NY 12223 Charles Donaldson, Esquire Assistant Attomey General New York Department of Law 120 Broadway New York, NY 10271

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REQUEST FOR ADDITIONAL INFORMATION THIRD INTERVAL INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES JAMES A. FITZPATRICK NUCLEAR POWER PLANT l

DOCKET NO 50-333 1.- RELIEF REQUEST PRR-02: -

L PRR-02 states that the standby liquid control pump (11P-2A or B) flow rate is determined L by measuring the change in the test tank water level. Does the accuracy of the flow rate determined by this method meet

• 2 percent, which is the OM-6 requirement for flow measurement instrumentation? If the accuracy does not meet i 2 percent, provide a justification for the altemative accuracy. :

l 2. REUEF REQUEST PRR-03:

L l Provide documentation that demonstrates that the standby liquid control pumps 11P-2A

, and B are not susceptible to the following degradation mechanisms that could rerutt in l

increased vibration levels seen at frequencies near and below the pump rotatior:al speed frequency: looseness of the bearings, misalignment, rubbing, oil whip, and impacts from rolling element bearing cage defects.

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3. RELIEF REQUEST PRR-05:

i PRR-05 states that liis not practical to establish a single repeatable reference point for the emergency service water pumps (46P-2A and B) because the pumps operate under

a variety of flow rate and differential pressure conditions. As discussed in Draft NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants," Section 5.2, "Use of Variable Reference Values for Flow Rate and Differential Pressure During Pump Testing,"

the use of pump curves may be acceptable provided the following elements are t

performed in preparing the pump curves:

(1) Curves are developed, or manufacture's pump curves are validated, when the pumps are known to be operating acceptably.

l l (2) The reference points used to develop or validate the curve are measured using -

instruments at least as accurate as required by the Code.

(3) Curves are based on an adequate number of points, with a minimum of five.

(4) Points are beyond the " flat" portion (Iow flow rates) of the curve in a range which

_ includes or is as close as practicable to design basis flow rates, l

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2-(5) Acceptance criteria based on the curves do not conflict with Technical Specification or Facility Safety Analysis Report operability criteria, for flow rate and differential pressure, for the affected pumps.

(6) If vibration levels vary significantly over the range of pump conditions, a method for assigning appropriate vibration acceptance criteria should be developed for regions of the pump curve.

(7) When the reference curve may have been affected by repair, replacement, or routine service, a new reference curve shall be determined or the previous curve revalidated -

by an inservice test.

Address each of these seven elements in the relief request and provide justification if the proposed altemative is not consistent with NUREG-1482, Section 5.2, guidelines.

4. RELIEF REQUESTS VRR-01 and VRR-03:

' It is not evident based on the information presented for the valves (02RV-71 A, B, C, D, E, F, G, H, J, K, and L; and 07SOV-104A, B, and C) that assigning a reasonable, objective acceptance criterion to an observable parameter, such as acoustics, temperature, flow rate, or AP, to measure stroke times is impractical or would result in hardship without a compensating increase in the level of quality and safety. If the stroke timing requirements cannot be met, please provide a basis in sufficient detail to justify a proposed altemative, following the applicable guidelines in NUREG-1482, Section 4.2,-

" Powered Operated Valves," and NUREG-1482, Appendix A, pp A-24 to A-34.

5. RELIEF REQUEST VRR-02:

OM-1, section 3.3.1.1, states that "[ tests prior to maintenance or set pressure adjustment, or both, shall be performed in the following sequence: (a) visual examination; (b) seat tightness determination; (c) set pressure determination; (d) determination of compliance with the Owner's set tightness criteria; (e) determination of electrical characteristics and pressure integrity of solenoid valves; (f) determination of pressure integrity and stroke capability of air actuator; (g) determination of operation and electrical characteristics of position indicators; (h) determination of operation and electrical .

characteristics of bellows alarm switch; and (I) determination of actuating pressure of auxiliary actuating device sensing element, where applicable, and electrical continuity.

~ For the ADS valves 02RV-71 A, B, C, D, E, F, G, H, J, K, and L, the licensee states that "the plant's test practices ensure that applicable tests specified in ANSI /ASME OM-1, section 3.3.1.1,' Main Steam Pressure Relief Velves with Auxiliary Actuating Devices,'

are performed and the entire valve operability is verified in accordance with Technical Specifications, but not in the sequence specified by OM-1, section 3.3.1.1." Provide details with respect to which of the above tests are out of sequence and the ramification of each out of sequence testing.

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6. RELIEF REQUEST VRR-06:

With regard to valves 66PCV-101,66TCV-107E,66TCV-107F,70TCV-120A, 70TCV-1208, 70TCV-121 A, 70TCV-121B, and 67PCV-101, specify the safety (including fail-safe) position (s) of each valve. If the valves are used only for system control, no relief is required since, OM-10, paragraph 1.2, excludes such valves from inservice testing. If a valve has a safety function to open and/or close and the stroke timing requirements cannot be met, please provide a basis in sufficient detail to justify a proposed attemative, following the applicabla guidelines in NUREG-1482, section 4.2.9, " Control Valves with a Safety Function," section 4.2.3, " Measurement of Valve Stroke Time," and NUREG-1482, Appendix A, pp A-24 to A-34, 1,

7. Provide piping and instrumentation drawings for the relief requests discussed in the October 21,1997 submittal. ,

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