ML20011A104

Forwards Clarification of Util Response to NUREG-0737,Item II.K.3.17 Re Rept on Outages of ECCS Licensee Rept & Proposed Tech Spec Change.Change Will Be Included in Revision 8 to FSAR

ML20011A104
Person / Time
Site:	Wolf Creek, Callaway
Issue date:	10/02/1981
From:	Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM NUDOCS 8110070263
Download: ML20011A104 (3)

Text

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SNUPPS Stenderdized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholes A. Petrick Rockville, Maryled 2085C Executive Director (301) 869 4010 October 2, 1981 SLNRC 81-116 FILE: 0541

, SUBJ: NUREG-0737,II.K.3.17 Mr. Harold R. Denton, Director Office of fluclear Reactor Regulation U. S. Iluclear Regulatory Comission Washington, D. C. 20555 Docket Nos. STN-50-482, STil 50-483, and STN 50-486

Dear Mr. Denton:

Per the request of Dr. Gordon Edison, a clarification to the SNUPPS response to the subject item is provided berewith. This FSAR change will be included in Revision 8.

Very truly yours,

-fM\C W

- Nicholas A. Petrick RLS/jdk to Enclosure [fh 1 cc: D. F. Schnell UE L~ OCT 7 ;ggy ,,8 G. L. Koester KGE - u.c.,,m, % A

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W. A. Hansen NRC/ CAL f T. E. Vandel NRC/WC / *:: 4

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PDR ADOCK 05000482 A PDR

SHUPPS

.18.2.17.13 Reduction of Challences and Failures ofd Relief Valvet--Feas_ibility Study and System Mo_ i fica-tion (II.K.3.16)

Not applicable to Westinghotne pressurized water reactors. .

18 2.17.14 Report on Outaces of Emercency Core-Coolinj g

- Systems Licensee Report and Fronosed Technical Specification Chances (II.K.3.17) .

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18.'2.17.14.1 NRC Guidance Per NUREG-0737 i Tosition Several components of the emergency core-cooling (ECC) systems are permitted by technical specifications to have substantial outage times (e.g., 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for one diesel-In addition, there generator; 14 days for the HPCI system).

are no cumulative outage time limitations for ECC systems.

Licensees should submit a report detailing outage dates and for all ECC systems for the last 5 years Jengths of of outagesThe report should also include the causes of operation.

the outages (i.e., controller failure, spurious isolation).

f Clarification 1

l The present technical specifications contain limits on

(, allowable outage times for ECC systems and components.

Ecwever, there are no cumulative outage tin.e limitations on l these same systems. It is possible that ECC equipn.ent could meet present technical si.ecification ' requirements but have a high unavailability because of frequent outages within the allouable technical specifications.

l The licensees should submit a report detailing outage dates t

and length of outages for all ECC systems for the last This f 5 years of operation, including causes of the outages.

l report will provide the staff with a quantification of

{ historical unreliability due to test and maintenance outages, which will be used to determine if a need exists for cumula-tive outage requirements in the te:hnical specifications.

Based on the above guidance and clarification, a detailed report should be submitted. Thd report(2)should cause contain (1) of the outLge dates and duration of outages; outage; (3) ECC systems or components involved in the outage; Test and maintenance are and (4) corrective action taken.

authges should be included in the above listings whichs to cover the last 5 years of operation. The licensee should propose changes to improve the availability of ECC equipment, -

if needed. .

Applicant for an operating license shall establish a plan to (Q) meet these requirements. Rev. 7 9/81 18.2-79 A ~~ '; __

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I SimPPS 18.2.17.14.2 SNUPPS Response I

The SNUPPS Utilities will provide safety system outage ,

information that is proposed by " Standard Technical Specifi- '

cations for Westinghouse Pressurized Water Reactors" (Rev. 3).

Specifically, the following will be provided in 30-dayi -

written reports:

r. -

S. Conditions leading to operation in afor dition degraded Operation mode or plant l

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. permitted by a Limiting Conshutdown required by a Limiting condition for Op ,

in addition, records will be retained of the maintenance, inspections, and surveillance tests of the principal items These records can be reviewed by related to nuclear safety.

the NRC for additional specific data on component availa-bility. sc]{Nsever The SNUPPS facilities will report safety system outages as This reporting .I consistent with 10 CFR 50.36 described above.

and ensures that the data requested by Item II.K.3.17 of NUhEG-0737 is available.

18.2.17.15 Modi fication of Automatic Depressurization System Logic--F,easibility for Increased

' Diversity for Souie Event Sequences (II .K.3.18 )

kd, Not applicable to Westinghouse pressurized water reactors.

l l

18.2.17.16 Interlock on Recirculation Pump Loops (II.K.3.19)_

l Not applicable to Westinghouse pressurized water reactors.

18.2.17.17 Restart of Core Soray and Low-Pressure Coolant-In3ection Systems (II.K.3.21)

Not applicable to Westinghouse prersurized water reactors.

18.2.17.18 Automatic Switchover of Reactor Core Tsolation Cooling System Suction--Verify Procedurer and Modify Design (II.K.3.22)

Not applicable to Westinghouse. pressurized water reactors.

I 18.2.17.19 Confirm Adequacy of Space Cooling for High-Pressure Coolant Inlection and Reactor Core Isolation Cooling Systems ( I I . K . 3 . 24 )_ s Not applicable to Westinghouse pressurized water reactors. .

Rev. 7 9/81 18.2-80 1

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o Il4 SERT i The documentation will include: (1) outage dates and duration.

(2) cause of the outage, (3) systems or components involved in the outage, and (4) corrective action taken.

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