ML20096A426

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Forwards Details Relative to Methodology Used in re- Evaluation of Capability of Two Suppl 3 HPCI MOVs to Perform Design Basis Function,In Response to 920219 RAI Re Generic Ltr 89-10,Suppl 3
ML20096A426
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/01/1992
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, NLR-N92050, NUDOCS 9205110059
Download: ML20096A426 (4)


Text

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a Puoi,c Service

[lectric and Gas Company

' Staen E. M.itenberger Pubbc Sordce Ehrtnc and Gas Company P.O. Box 236. Hancocks Bndge. NJ 08038 609-339-1100 VeeOwem pod Che' Nocear 0"1cer WAY 01 I!G2 NLR-N92050 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RESPONSE TO FEBRUARY 39, 1992 RAI GENERIC LETTER 89-10 SUPPLEMENT 3 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 i

The purpose of this letter is to respond to the February 19, 1992 request for additional information (RAI).

This RAI requested that PSE&G re-evaluate the capability of the two Supplement 3 HPCI MOVs to perform their design basis functions with consideration given to diag..ostic equipment inaccuracies.

We have re-evaluated the capability of the valves to close under design basis conditions and the ability of the motor operators to withstand the associated maximum thrusts with consideration given to diagnostic equipment inaccuracies.

This re-evaluation is available for your review.

Our re-evaluation of over-thrust considerations is limiced to an assessment-of the motor operator.

Once we receive our weak-link and revised seismic analyses from the valve manufacturer, we will re-review the maximum measured thrust values relative to valve, yoke and bolting limitations and-further determine the acceptability of the current torque switch settings.

When this re-review is completed, the NRC will be notified and the results will be available for review.

The attachment to this letter provides some details relative to the methodology used in the re-evaluation.

Should you have any quistions or comments on this transmittal, do

-not hesitate to contact us.

Sincerely,

/f buV' Ly i

bV I

9205110059 920501 I!)U I b

PDR-ADOCK 05000354 i

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PDR I

9 Document Control Desk 2

g4y 01 19%?

NLR-N92050 C

Mr. T.

T. Martin, Administrator - Region I U.-S.

Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.

S.

Dembek, Licensing Project Manager U.

S.

Nuclear Regulatory Commission one White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr.

T. P. Johnson (S05)

USNRC Senior Resident Inspect';r Mr.

K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 l

1 l

1 Ref:

NLR-N92050 STATE OF NEW JERSEY

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SS.

COUNTY OF SALEM

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S.

Miltenberger, being duly sworn according to law deposes and says:

I am Vice President and Chief Nuclear Officer of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated WAY 01 1116 2 concerning the Hope Creek Generating Station,'are true to the best of my knowledge, information and belief.

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f Subscribed and Sworn to before me this fh day of t' !Nhk 1992 t$llbtAa IYQ1k

!otaryPdblicofhewJersey N

SHERRY L CAGLE NOTARY PUBUC 0F NEW JERSEY My Commission Empires March 5,1997 My Commission expires on

. ATIN3 MENT 4

INPGMATICH CCNCEFNING HPCI M IE-INAIDATICH NIR-N92050 GENERIC II:rITR 89-10 SUPPIINENT 3_

IDIE CREEK GENERATING STATICH FN'IT3TY 00ERhTING LICINSFS NPF-57 DOCKE:P NO. 50-354 he request for additional infomation required that we re-evaluate the -

capability of the Supplement 3 HPCI Ms to perfom their. design basis functions in light of diagnostic equipnent inaccuracies. We design basis for the HFCI inboard ard outboard isolation valves is to close on the limit switch, not the torque switch.

W e ITI HOVATS Special Test Report 2.0, Rev. 1, "Open Versus Close Test Program Final _ Report", dated March 13, 1992 characterizes newly determined M ATS:

equipnent inaccuracies. - This report includes a flow chart that gives direction on how to determine the correct output thrust of Ms tested with the MOVATS 7MD methodology._ 2 e first logic decision is based on whether the close torque switch is in the control circuit.

If the answer to this question is "no",

there is'no requirement to perform further minimm thrust calculations. Since the design basis _for the subject HPCI valves is to close on limit and not on torque,-this question-is answered "no" and the valves are considered capable of perfoming their ' design basis functions after evaluation of the effect of diagnostic equiptent inaccuracies. We basis for this corrlusion is further d%mM below. -

The. electrical control logic for the imW-F002 and 1 FUN-F003 valves bypasses the torque switch for autcznatic close initiation signals. S us, the valves

.will close until the 1S-15 contacts open. At this point, control reverts to the torque switch. ~ For this control scheme, the IS-15 is generally set near the mint that the torque switch would open; therefore,. disc wedging under torque switch bypass. control is similar to that with torque switch control.

Urder static system conditions, the most recent }0 VATS diagnostic static test results indicate that IS-15 opens ~at 26,190_lbs. of measured thrust on 1FDN-F002 and:at 14,300 lbs. of measured thrust on 1FIIN-F003.- The test traces irdicate that these thrusts are wedging loads; therefore, the valves flow orifices are fully blocked. Since the valves positica seat, as a minimum,

-for' design basis' accident corditions, valve closure is independent of torque switch setting and the thrust associated with torque _ switch trip.- Output

-thrust availability under torque switch bypass control-is. limited to the actuator output' rating and-not the torque switch setting; therefore, the -

closure position is assured, regardless of thrust requirements, as lory as operator capability envelopes the requirement.

'In order to address the, potential' for an actuator overthrust cordition under statWloadings, we also reviewed the static test traces for maximum measured thrust.. We then cxrpared these values, :34,000 lbs ard 36,500 lbs, for 17U N-F002 and F003, respectively, against the ITI.MOVATS Special Test Report 2.0,. Rev.1, Appendix B graph for the SMB-1 Bounding Model. Re Bounding Model represents Path 1 methodology which is noted by MOVATS to be conservative. Se above measured thrust values-fall well within the 45,000'lb. nominal-rating for the-actuator for the corresponding actual' thrust value. Therefore, the actuator is not overthrusted on either valve. It should be noted that this evaluation is limited to an x-ent of the motor operator. Once we receive our weak-link ard revised seismic analyses from the valve manufacturer, we will re-review the raximum measured thrust values relative te valve, yoke ard bolting limitations ard determine the acceptability of the current torque switch settings. - When the re-review is empleted, the IRC will be notified and

-tho results will be available for review.

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