ML20010H307

Application for Amend to DPR-6,changing Tech Specs to Incorporate Revised 10CFR,App G Cooldown,Heatup & Hydrotest Limitations

ML20010H307
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/18/1981
From:	Hoffman J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML20010H308	List: ML20010H307 ML20010H309 ML20010H311
References
NUDOCS 8109240324
Download: ML20010H307 (3)

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Consumers David P Hoffman Nudear Lucensing Admmustrator Company General offices: 1945 West Pernall Road, Jackson, Me 49201 * (517) 788 1636 DI k

September 18, 1981 S.,,

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Att Mr Dennis M Crutchfield, Chief

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Operating Reactors Branch No 5 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG a..,cK POINT PLANT - TECHNICAL SPECIFICATION CHANGE REQUEST - REACTOR VESSEL CRITICALITY, C00LDOWN, HEATUP AND HYDROTEST LIMITATIONS Attached are three (3) originals and thirty-seven (37) copies of a request to change the Big Rock Point Technical Specifications.

This change incorporates the revised 10CFR50, Appendix G limits. uveral differences from the existing Technical Specification table result from this change and include the following:

- fue data is presented in tablular form and not as a graph.

- The reactor vessel metal temperature is used to dictate pressure versus temperature limits instead of the indicated reactor water temperature. Four beltline indicators (thermocouples at elevation 604')

l are at 0*, 90*, 180*, 270* ; howev-r, administrative controls will be established requiring all pointe on the reactor vessel and steam drum to l

be greater than the required temperature limit. This will provide administrative margin on Technical Specifications during NSSS 00/

bydrostatic tests and plant operation.

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- The minimum temperature where criticality (except low power physics 3 [t/ O testing) can occur will be 90 F.

This is in contrast to the 190*F limit as it exists now.

This results from an alteration 'n the NRC lower w[c[So/.

l limits for criticality (Flange material reference tesperature 30*F +

j 60*F, reference 10CFR50 Appendix G paragraph IV.A.?'.

Thislowerlimitgyooo,oe does not prevent low power physics testing critical

- The new limits provide more flexibility when it come

o heatup and cocidown rates. The limits become more restrictive as the heatup/cooldown rates increase.(ie, more restrictive at 100*F/hr than at 20*F/hr).

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Dennis M Crutchfield, Chief 2

Big Rock Point Plant?

September 18, 1981 Interim measures between expiration of existing Technical Specification limits and NRC approval of the proposed limits have been established. These measures provide for use of the most conservative limits between both the existing and the proposed Technical Specifications. Since these temporary measures may not permit performance of an NSSS hydrostatic test, it is requested that approval of this Technical Specification change be expedited.

The requested change involves a single safety issue. Therefore, a check in the amount of $4,000 is attached pursuant to 10CFR170.22, Class III change.

_$Y David P Hoffman Nuclear Licensing Administrator CC JGKeppler, USNRC NRC Resident Inspector L

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CONSUMERS POWER COMPANY Docket 50-155

• Request for Change to the Technical Specifications License DPR-6 For the reasons here.nafter set forth, it is requested that the Technical Specifications contained in the Facility Operating License DPR-6, Docket 50-tSL, f esued to.'onsumers Power Company on May 1,1964, for the Big Rock Point Plant be changed as described in Section I belcw:

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Changes Replace Figure '4-1 Big Rock Point - 1:eactor Vessel Criticality Cooldown, Heatup and Hydrotest Limitations with Table 4-1 Hydrostatic Test Pressure / Temperature Limits, Heatup Pressure / Temperatures Limits and Cooldorn Pressure / Temperature Limits.

(Table 4-1 is attached).

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Discua: ;9n The enclosed Appendices, A through D, provide the bases for this Techni-cal Specification change. The limits specified by this change are being submitted because the fluence at the inner vessel wall location at which the existing technical specification limits apply have expired. Appen-dix B references an analysis from the 125 capsule. The report " Analysis of Capsule 125 from the Consumers Pcwer Company Big Rock Nuclear Plant Reactor Vessel Radiation Surveillance Program" is enclosed as required by 10CFR50 Appendix H.

III. Conclusion Based on the foregoing, both the Big Rock Point Plant Review Connittee and the Safety and Audit Review Board have reviewed this change and fiu d it acceptable.

CONSUMERS POWER COMPANY By

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R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me thia 18th day of September 1981.

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M-Helen I Dempski, Notpfy Public Jackson County, Michigan My commission erjires December 14, 1983.

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