ML20135A849

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Forwards Reg Guide 1.97 Nuclear Station Mods (Nsms) to Be Delayed Until 1988 Refueling Outage.Delaying Implementation of Nsms Will Allow Other Critical Mods to Be Implemented During Next 2 Yrs
ML20135A849
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 08/30/1985
From: Tucker H
DUKE POWER CO.
To: Adensam E, Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8509100292
Download: ML20135A849 (3)


Text

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Dmm Pownn Godmtxy P.O.150 X 3 310 0 Cita RI.OTTE. N.C. 20242 ILO.D. TUCKER vice ref9E9ETT utzenon wtxsaan reonceveow (704) 373-4331 August 30, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Ms. E. G. Adensam, Chicf Licensing Branch No. 4

Subject:

Duke Power Company McGuire Nuclear Station Docket Nos. 50-369 & 50-370

Dear Mr. Denton:

By lutter dated March 29, 1984 Duke Power provided Revision 3 to our response to Supylement I to NUREG-0737 for McGuire Nuclear Station.

This revision included the Regulatory Guide 1.97 Report along with other items.

This RG 1.97 Report included certain specific commitments to modify McGuire during the first refueling outage of each unit after January 1986.

This was to be contin-gent upon equipment availability.

Duke has reviewed this co=mit=cnt and, for the reasons dist.usned in the following paragraphs, is revising the commitment date to the refueling outages for each unit that initiate in 1988.

A large number of outage-related, regulatory-tequired Nuc1 car Station Modifications (NSM's) have been identified for impicmentation over the next two refueling outages (1986, 1987) for each unit at McGuire Nuclear Station. Approximately one half of the NSM's planned for unit i EOC 3 and unit 2 EOC 2 are regulatory-required. Virtually all of the NSM's presently planned for unit 1 EOC 4 and unit 2 EOC 3 are regulatory-required.

This heavy work load of regulatory requirements forces significant delays in the design and implementation of 7

critically important personal safety, ALARA, reliability, and radwaste modifi-cations.

Delaying implementaiton of the RG 1.97 NSM's listed on the attached table will allow other critical (but not regulatory-required) codification vork to be implemented during the next two years.

Additional factors which have been considered include the fact that Duke has given high priority to the regulatory required Human Engineering Deficiancy (HED) modifications.

Much of the HED work will occur over the next two years.

Also, the potential congestion and interferences in the Control Room if both HED's and Reg. Guide 1.97 NSM's are implemented during the same outages are of concern.

00 8509100292 050830 o o PDR ADOCK 05000369 F

PDR i

Mr. Harold R. Denton, Director i

August 30, 1985 Page 2 If there are any questions regarding this commitment, please advise through normal licensing channels.

Very truly yours,

}4 / B. T J x Hal B. Tucker RLG/hrp Attachment cc:

Dr. J. Nelson Grace, Regional Administrator i

U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900

?

Atlanta, Georgia 30323 Mr. Darl Hood, Project Manager 1

Division of Licensing Office of Nuclear Regulatory Commission Washington, D. C. 20555 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station a

e E

f McGuire Nuclear Station RG 1.97 NSM's to be Delayed to Refueling Outages that initiate in 1988 Unit 1 Unit 2 NSM Description NSM Number NSM Number Changeout VL RTD's - Loops 5000, 5010, MG-1622 MG2-484 5020, and 5030 Provide s' ;elding for EMF's 35, 36, and MG-1623 MG2-588 37, and provide remote sample point for unit vent.

Changeout NC PRT RTD - Loop 5350 MG-1624 MG2-485 Changeout ND Heat Exchanger RTD's - Loops MG-1625 MG2-488 5000 and 5120.

Provide IE powered position indication MG-1626 MG2-486 for Valves NF-228A, NF-234A, and NF-233B Install two additional Class lE channels MG-1627 MG2-492 of full range neutron instrumentation.

Provide IE powered position indication hr-1628 MG2-487 for Valves CF-26, CF-28, CF-30 and CF-35.

Provide isolation devices between post MG-1630 MG2-490 accident indicators and non qualified equipment.

Changeout NS flow transmitters - Loops MG-1631 MG2-489 5020 and 5030.

Changeout SM flow transmitters - Loops MG-1661 5000, 5010, 5020, 5030, 5040, and 5050.

N/A j

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