ML17157B860

Forwards Supplemental SE Accepting Util Response to Sbo. Confirms Licensee 920612 Commitment to EDG Reliability Program Which as Min Contains Five Elements of RG 1.155, Section 1.2,until Resolution of GI B-56

ML17157B860
Person / Time
Site:	Susquehanna
Issue date:	06/16/1992
From:	Maxwell G Office of Nuclear Reactor Regulation
To:	Keiser H PENNSYLVANIA POWER & LIGHT CO.
Shared Package
ML17157B861	List: ML17157B860 ML17157B862
References
REF-GTECI-B-56, REF-GTECI-EL, RTR-REGGD-01.155, RTR-REGGD-1.155, TASK-B-56, TASK-OR TAC-M68613, TAC-M68614, NUDOCS 9206260304
Download: ML17157B860 (8)

Text

'9206260'304:920616 PDR 'DOCK 05000388.

'PDR J

SUS(UEHANNA STEAM ELECTRIC STATION SE TABLE I

SUMMARY

OF RELIEF REQUESTS

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;: -',.jSect ion ',Xl:,::,':Re'quii'emerits:,:,';:.:Fj~X

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~.:;:.i::.i:.:;:;::;,: ':t ~~,".:.'.Prop'o's'ed A I terna't'iye',::,:,','.',.:g PRR-52 N/A IMP-3210, allowable ranges of inservice test quantities Various pumps in the RHR, Core Spray,

ESW, RHRSW, HPCI, and SBLC Systems

1. The values of pump flow and pressure, corrected for the effects of instrunent accuracy shall be compared to the allowable ranges for the corresponding test quantities, from Table IMP-3100-2, for determination of acceptability.

Preapproved GL 89-04, Relief not evaluated in SE.

2. Instrunent accuracies for use in these corrections shall be determined, as

needed, by calibration of the flow and/or pressure instrunents utilized for the pump test.

3. Actual accuracies for use in these corrections shall conform to the acceptable instrunent accuracies established for flow instrunents and for pressure instrunents by Table IMP-4110-1.

PRR-54 PRR-55 H/A H/A IWP-4310, bearing temperature measurement IMP-4120, required range of test instrunents Various pcs in the RHR, Core Spray, ESM, and RHRSW Systems Various pcs in the RHR, Core Spray and HPCI Systems Hone Utilize permanent plant pump suction pressure instrunents for ISI pump test suction pressure measurements in RHR, Core Spray, and HPCI Systems.

Preapproved GL 89-04, Relief not evaluated in SE.

Preapproved GL 89-04, Relief not evaluated in SE ~

PRR-56 PRR-63 2.5 H/A IMP-3100, inservice test procedure requirement for pmp speed to be adjusted to the reference speed.

H/A 1P204 and 1P209 (Unit 1) 2P204 and 2P209 (Unit 2)

Combination pumps located in the HPCI System H/A When pump test speed differs from the reference speed by a measurable amount (10 RPH, or greater),

the corrective action analysis, permitted by paragraph IMP-3230(c) may include a correcttve calculation.

Request Withdrawn Relief Denied.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 June 16, 1992 Docket Nos.

50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

SUBJECT:

SUPPLEMENTAL SAFETY EVALUATION (SSE)

ON THE STATION BLACKOUT RULE FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NOS.

M68613 AND M68614)

The Station Blackout (SBO) Rule requires licensees to submit information as defined in 10 CFR 50.63 and provide a plant and schedule for conformance to the SBO Rule.

The Pennsylvania Power and Light Company's (the licensee) responses to the SBO Rule were provided by letters from H.

W. Keiser dated April 17, 1989, April 17,

1990, and February 27, 1991, to the U.S. Nuclear Regulatory Commission.

This was followed by the licensee's written response dated August 1, 1991, to questions during the June 14,

1991, telephone conference.

By letter dated January 14,

1992, the staff transmitted a Safety Evaluation (SE) on the above submittals that found the licensee's proposed method of coping with an SBO to be incomplete.

The licensee responded to this SE by letter from H.

W. Keiser, dated March 13,

1992, and its supplements dated April 14, 1992 and May 13, 1992.

The staff has reviewed the licensee's responses to the staff's January 14, 1992 SE pertaining to the SBO Rule and finds the licensee's response to be acceptable except that until Generic Issue (GI) B-56 is resolved, the licensee committed, during a telephone conversation on June 12, 1992, to an emergency diesel generator reliability program which as a minimum contains the five elements of Regulatory Guide 1. 155, Section 1.2.

Enclosed is the staff's SSE.

Therefore, no further submittals are required.

It is the staff's position that the licensee must be in full compliance with the SBO Rule within 2 years after receipt of this SSE in accordance with 10 CFR 50.63(c)(4).

Therefore, this requirement should be implemented to ensure complete compliance with the SBO rule as indicated in the staff's SE and SSE.

The licensee should maintain all documentation in support of its SBO submittals in its files fo} possible future NRC audit.

tl nr

Hr. Harold W. Keiser June 16, 1992

This SSE documents the NRC's final regulatory assessment of the licensee's

'proposed conformance to the SBO Rule and closes TAC Nos.

H68613 and H68614.

, If there are any questions please contact me on (301) 504-1447.

Sincerely,

/s/

Enclosure:

Supplemental Safety Evaluation cc w/enclosure:

See next page DISTRIBUTION:

. Docket File NRC 5 Local PDRs PDI-2 Reading SVarga JCal vo CHil 1 er MO'Brien(2)

JRaleigh GMaxwell OGC AToalston PTam ACRS(10)

EWenzinger, RGN-I

JWhite, RGN-I

• Previously Concurred George F. Maxwell, Acting Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation OFFICE PD, PDI-PH SELB*

PDI-2 P

NAME MO'BR EN JRAL

tlc ATOALSTON CHI OATE t2

(@92 I~ 92 06 16 92 92 OFFICIAL RECORD COPY FILENAME: A:iSU68613. SER

,1 l

I

'I J

Mr. Harold W. Keiser June 16, 1992 This SSE documents the NRC's final regulatory assessment of the licensee's proposed conformance to the SBO Rule and closes TAC Nos.

M68613 and M68614.

If there are any questions please contact me on (301) 504-1447.

Sincerely,

Enclosure:

Supplemental Safety Evaluation cc w/enclosure:

See next page George

. Maxwell, Acting Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Mr. Harold W. Keiser Pennsylvania Power

& Light Company Susquehanna Steam Electric Station, Units 1

& 2 CC:

Jay Silberg, Esq.

'haw,

Pittman, Potts

& Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U.

S. Nuclear Regulatory Commission P.O, Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection

.Resources Commonwealth of Pennsylvania P. 0.

Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603 Mr. Robert G.

Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North, Ninth Street Allentown, Pennsylvania 18101