ML20101K516

Application for Amends to Licenses DPR-24 & DPR-27, Consisting of Change Request 33,revising Radiological Effluent Tech Specs

ML20101K516
Person / Time
Site:	Point Beach
Issue date:	12/20/1984
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20101K520	List: ML20101K516 ML20101K531
References
NUDOCS 8412310382
Download: ML20101K516 (4)

Text

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lHsconsin Electnc mmcwa 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 i December 20, 1984 4

i Mr. R. R. Denton, Director

}. ,0ffice of Nuclear Reactor Regulation a

U. S. NUCLEAR REGUIATORY CONNISSION Washington, D. C. 20555

+ Attention: Mr. J. R. Miller, Chief operating Reactor, Branch 3 Gentlemen DOCKETS 50-266 AND 50-301 l RADICLOGICAL EFFLUENT TBCENICAL'$FECIFICATIONS i CHANGE RECUEST 33 POINT BEACM NOCLEAR F' ANT, UNITS 1 AND 2

[ On October 7,1983, Wisconsin Electric Power Company, l

Licensee for the Point Beach Nuclear Plant, Units 1 and 2, submitted i

a modification to its licenso amendment application and Technical Specification Chango Request 33. That submittal included revised

, proposed Radiological Effluent Technical Specifications (RETS) and was a modification to our previous RETS submittals, the first of which was on June 4, 1976. Your letter dated July 18, 1984 provided comuments and suggestions for additional changes to our proposed

, RETS. These changes were discussed during a meeting held on October 11, 1984 in your Bethesda, Maryland offices. Agreement was

' reached on these points, and we committed to provide you a revision of our RETS application by December 20, 1984.

Attached is a complete proposed set of RETS pages for l

L the Point Beach Nuclear Plant. These proposed pages supersede in their entirety the Technical Specification pages provided with our ,

October 7, 1983 letter and all previous submittals. The following is a brief discussion of the principal changes included with this latest revision of our RETS application:

1. As discussed during the meeting on October 11, these proposed RETS have been moved to a separate Section 15.7 of the Technical Specifications. Radiological effluent and envirossental monitoring specifications 3 formerly included in Sections 15.3.9, 15.4.10, proposed 15.4.17, and 15.5.1 have been moved to this new section.

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I Mr. H. R. Denton ' December 20, 1984 '

A licensed operator examination disclaimer, which is consistent with the NRC Operator Licensing Branch position statement, has been included. This new section also includes RETS-related definitions which supplement Section 15.1 of the Technical specifications.

2. As requested by your staff, we have made the RETS instrumentation operability requirements tables consistent with the surveillance requirements tables. The annual calibration interval has been changed to a refueling interval basis (not to exceed eighteen months) to be consistent with the rest of the Technical specifications. A specification for a Waste Gas Hold-Up System Explosive Gas Oxygen Monitor has been included as requested. Please observe that no hydrogen monitoring requirements have been included, because the waste gas cover system always includes hydrogen in excess of two percent. Explosive gas monitoring is, therefore, based on oxygen monitoring.

3. In section 15.7.5 the annual release objectives have been redefined as release limits. The affluent monitor set-points will be established to ensure that radioactive materials released as effluents do not result in concen-trations to unrestricted areas in excess of limits specified in 10 CFR 20, Appendix B.

4. The tritium adjustment specification has been revised to include a proportioning formula between gaseous and liquid limits, as requested by your staff.

5. A specification to conduct monthly release and dose calculations, if twice the quarterly release limits are exceeded, has been provided, as requested.

6. We have elected to retain the specification we originally proposed for radioactive effluent waste treatment. As suggested by your staff at the October 11 meeting, we have prepared a cost-benefit analysis for operation of the Point Beach affluent waste treatment equipment. The preliminary result of the analysis demonstrates that the proposed operating specifications are more cost effective than operating the systems whenever projected releases may exceed 1/48 of the annual limits. The details of the cost-benefit analysis will be provided to support this conclusion with our Off-8ite Dose Calculation Manual (ODCM) submittal.

7. Total dose and explosive gas mixture specifications have been provided.

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1 December 20, 1984 Mr. H. R. Denton

8. The radioactive 11guld weste and gaseous  !=131 weste sampling analysea and analysis tables have been revised.The LLD for tritium in d the have been added to the tables.the gaseous waste sampling ta The re-SS LLD for the noble gas monitor has been added.The average annual analysis requirement has been deleted.

quantity of re-55 roleseed from Point Beach was settmated assuming a maximuai theoretically derived real5/re=59 Assuming this ratio, re=SS would have ratio of 50.

accounted for an average annual average of 0.1 Beach during the period 1979 to 1983.

dose from liquid effluente relonned from Fotnt p

9. As discussed in our previous mutaittale, a specifloation for a Curie content limit for gas storage tanke han notWe been included. we have previounty mutaitted, and that the justification i

no additional information in required.

utring

10. As requested, we have proposed a opeof f tention re a weighted aum calculation of detouted radionuolinan if the thanm asured value twenty-five percentof of a detected radionuotide the notifloation level. le more 11.

An Interinboratory Comparison Program specification la included at 15.7.7.R.

12. Periodio audit requirement a have been includednad in ite Spooltication 15.7.8.2 for the 00CM, the WP, implementing procedures, and These audits thepreviovelp worn radiologioni envitormenta propo**d monitoring program.

under the cognhaance of the of f=81te havtow Ctemittee (OM They were moved to a esparate naution at the requanti the conducted be C(monittee members.

by off-site personnel, will be provided to the 08MC and Vace President-Muolear tower.

13. A specification for reporting of changen to the OfCHne patt of the and Procene control Program LPCP)

Monitoring Report has baan included At 18.7.6.A.4.

specification 15.7.8.5 has ateo been maded to r* quire reporting of major changes to the radionotive waste treatment system.

As required by 10 CrR 50.91(a), we have evaluated theos changes in accordance wath the standarda in 10 CfM 00 93 with respect to the innus of whether these changes onnalitute aMecause these c significant hasards consideration.

of additional limitations, restrictions, and conttola not pramently

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