ML20092N266

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Informs That Operator Response Times Observed During Steam Generator Tube Rupture (SGTR) Simulations as Documented in Section 5 of Ref Rept,Support Operator Response Time Assumed in plant-specific SGTR Analysis
ML20092N266
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 02/21/1992
From: Feigenbaum T
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-92021, NUDOCS 9203020090
Download: ML20092N266 (2)


Text

l I

l New Hampshire Y

k Ted C, Feigenbovm hewident ond Chief t servine Offuer N YN. 92021 February 21, 1992 United States Nuclear llegulatory Commlulon Washington, D.C.

20555 Attention:

Document Control Desk

References:

(a)

Facility Operating License No. NPF 86, Dottet No. 50 443 (b)

NilY Letter NYN 91061, dated April 16,1991, ' Analysis of a postulated Design liasis Steam Generator Tube Rupture for Seabrook Station

  • T.C.

Felgenhaum to USNRC

Subject:

Steam Generator Tube Rupture Operator Response Times

(

Gentkmen:

New Hampshire Yankee (HlY) submitted a report entitled " Analysis of a postulated Design liasis O am Generator Tube Rupture for Seabrook Station" on April 16, 1991 l Reference (b)], The operator response times auumed in the Steam Generator Tube Rupture (SGTit) analysis were derived f rom times observed during SGTR simulation runs on the Seabrook Station plant specific training simulat,r and by plant walldown. The simulations were perfortned by two NilY operating crews using plant specific emergency operating I

procedures and design basis SGTR scenario assumptions.

The operator response times observed during the SGTR simulations as documented in Section 5 of the report, suppo-t the operator act.panse times auumed in the plant specific SGTR analysis.

The NRC has requested that NilY provide further validation of the operator response times arsumed in the plant specific SGTR analysis by conducting additional operating crew design basis SGTR simulations to ensure that at least five of the six operating creu base participated.

At least three NilY operating crews will perform a design basis SGTit simulation during their scheduled requalification training at the simulator facility in addition to the two crews which have already participated, New llampshire Yankee intends to include the design basis STOR simulation in the six week operator requalification period, which is scheduled to be completed in March 1993. This schedule will minimire conflict with the Fall 1992 refueling outage and the Fall 1992 NRC license examinations. Upon completion of the SGTR simulations, NHY will evaluate the observed operator action times vis a-vis those assumed in the SGTR analysts. in the event that the observed operator action times do not support the times assumed in the current design basis SGTR analysis l Reference (b)l, NiiY will revise and resubmit the SGTR analysis to the NRC.

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9203020090 920221 PDR ADOCK 05000443 P

PDR s

New Hampshire Yonkee Division of Public Service Company of New Hampshire

- OI P.O. b 300

  • Seabrook, NH 03874
  • Telephone (603) 474 9521

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Unittd States Nuclear llegulatory Comrnission l'c bs u as y 21, 1992 Attention:

Docurnent Control Dest l' age tw o Should you have any lusther questions regarding this innlict please contact hir. Jarnes h1. Peschel, llegulatory Cornpliance hianager, at (t.03) 474 9521 extension 3772.

Very truly yours, )

(hE&f 4

A Ted C. l'Eipubauru, '

TCP: A LI.

cc:

hit. Thornas T. hiattin Ittglonal Adtninistrator U.S. Nuclear Itegulatory Corutnission Itcgion i 475 Allendale lload King of Prussia, PA 19406 Mr. Gordon E !!dison, St. Project Af anager Project Directorate 13 Division of f(cattor l'rojects U.S. Nuclear llegulatory Commission Washington, DC 20$$$

hit. Noel Dudley NitC Senint itesident inspectoi P.O. Ilox 1149 heabronk, Nil 03874

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