B14258, Informs of Commitment to Perform 18-month PORV Stroke Test During Mode 3 or 4 Only When Entering Into Mode 3 or 4 from Higher Mode Operations (Modes 1 or 2),in Response to GL 90-06 & NRC Ltr

Informs of Commitment to Perform 18-month PORV Stroke Test During Mode 3 or 4 Only When Entering Into Mode 3 or 4 from Higher Mode Operations (Modes 1 or 2),in Response to GL 90-06 & NRC Ltr

ML20127M469
Person / Time
Site:	Millstone
Issue date:	10/28/1992
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR B14258, GL-90-06, GL-90-6, TAC-M77362, TAC-M77432, NUDOCS 9211300225
Download: ML20127M469 (3)

Text

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P O BOX 270 k L J 7EC2"C H ARTFORD. CONNECTICUT 0618 S0270 (203) 665-5000 October 28, 1992 DILeket No. 50-421 B14258 Re: GL-90-06 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Fower Station, Unit No. 3 Generic Letter ' 06, " Resolution of Generic Issue 70,

' Power _-Operated Relief Valve and Block Valve Reliability,' ar a Generic Issue 04, ' Additional low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10CFR50.54(f),"

(TAC Nos. M77362 and M77432)

In a letter dated June 25, 1990,(D the By letters dated December 21, 1990,(p)RCissuedGenericLettergGL)90-06.

and March 21, 1991,( Northeast F" clear Energy Company (NNECO) on behalf of Millstone Unit No. 3, submitted initial and revi.ed responses to the Staff.

(1) James G. Partlow letter to All Pressurized Water Reactor Licensees and Construction Permit Holders, " Resolution of Generic Issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,' and Generic Issue 94,

' Additional Low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10CFR50.54(f)," dated June 25, 1990.

(2) E. J. Mroczka letter to the U.S. Nuclear Regulatory Commission, "haddam Neck Plant, Millstone Nuclear Power Station, Unit Nos. 2 and 3, Generic

' etter 90-06, Resolution of Generic Issue 70, ' Power-0perated Relief Valve and Block Valve Reliability,' and Generic Issue 94, ' Additional Low-Temperature Overp essure Protection for Light Water Reactors,' Pursuant to 10CFR50.54(f)," dated December 21, 1990.

(3) E. J. Mroczka letter to the U.S. Nuclear Regulatory Commission, "Haddam Neck Plant, Millstone Nuclear Power Station, Unit Nos. 2 and 3, Generic-Letter 90-06, Resolution of Generic Issue 70, ' Tower-0perated Relief Valve and Block Valve Reliability,' and Generic Issue 94, ' Additional Low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10CFR50.54(f)," dated March 21, 1991.

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, UtS. Nuclear Regulatory Commission B14258/Page 2 October 28, 1992 In a letter dated August 24, 1992,* the NRC stated that NNECO's response did not adequately meet the Staff position regarding the 18-month power-operated relief valve (PORV) stroke testing. Specifically, the Staff is not accepting Mode 5 (Cold Shutdown) testing simply because it :is allowable by the ASME Code or that the NRC-approved In-Service-Test (IST) Program includes Mode 5 for this particular test. The Staff further restated its position wnich requires the 18-month PORV stroke test to be performed during Mode 3 (Hot Standby) or Mode 4 (Hot

. Shutdown) and in all cases prior to establishing cnnditions where the PORVs are used for low-temperature overpressure protection (LTOP).

NNEC0 has reviewed its earlier position and hereby commits to perform the 18-month PORV stroke test during Mode 3 or Mode 4 only wher entering into Mode

' or 4 from higher mode operations (Modes-1 or 2). _ This test will be a ' static test, whereby the PORV will be exposed to Mode 3 or 4 temperatures, and then isolated from the. primary system and tested to verify valve operability. A license amendment request for the Millstone Unit No. 3 Technical Epecifications will be processed to include the above test. An amendment request will be

submitted to the NRC by the end of January 1993. The surveillance procedures

. related to this test are being modified to -reflect this test and will be i implemented upon issuance of the amendment.

i 4 In addition, the DORVs are bein.g, and will continue to be, demonstrated operable

in all cases prior to establishing conditions where the PORVs are used for LTOP j (Millstone Unit No. 3 Technical Specification 4.4.9.3.1).

We hope you find the above information resper.sive to your request. If ycu should have any questicas on the above, please contact us.

Very truly yours,

! NORTHEAST NUCLEAR ENERGY COMPANY -

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!_ J. FqOpeka .O _

l Executive Vice Fresident cc: See Page 3

! (4) V. L. Roone.y letter to J. F. Opeka, " Staff Review of Generic Letter 90-06, l

' Resolution of Generic Issue 70, ' Power-0perated Relief Valve- and Block Valve Reliability,' and Generic Issue 94, ' Additional low-Temperatu.'e Overpressure Protection for Light-Water Reactors,' Pursuant to.

10CFR50.54(f),'" dated August 24, 1992.

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U S. :luclear Regulatory Commission B14258/Page 3 October 28, 1992 i cc: T. T. Martin, Region I Administrator

V. L. Rooney, NRC Prcject Manager, Millstone Unit No. 3 P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2, j and 3 Subscribed and sworn to before me this Of day of Ob d , 1992 l [c,[f4 C/, Al .-hL NC 9 l

Notary Public ,/

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