ML20086U422

Application for Amend to Licenses DPR-24 & DPR-27.Amend Incorporates Changes to Tech Specs Re Accident Monitoring Instrumentation to Be Installed Per NUREG-0737 Requirement

ML20086U422
Person / Time
Site:	Point Beach
Issue date:	02/29/1984
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20086U423	List: ML20086U422 ML20086U427
References
RTR-NUREG-0737, RTR-NUREG-737 GL-83-37, TAC-54559, TAC-54560, NUDOCS 8403070255
Download: ML20086U422 (4)

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>Hsconsin Bectnc mwea courany 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 February 29, 1984 CERTIFIED MAIL Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKETS 50-266 AND 50-301 SPECIFICATIONS FOR TMI BACKFIT INSTRUMENTATION TECHNICAL SPECIFICATION CHANGE REQUEST NO. 96 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with Sections 50.59 and 50.90 of 10 CFR 50, Wisconsin Electric Power Company (Licensee) hereby requests amend-ments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The purpose of these amendments is to incorporate changes into the Point Beach Technical Specifications which primarily concern accident monitoring instrumentation that will be installed as requested by the NRC in NUREG-0737, " Clarification of TMI Action Plan Requirements". Specific changes addressed by the application are discussed in the following.

Proposed Technical Specification pages with the changes identified by. margin bars are enclosed with this application.

Generic Letter No. 83-37 dated November 1, 1983 discussed a number of NUREG-0737 items which were scheduled for implementation after December 31, 1981. That letter included guidance for submitting Technical Specification changes which would cover those systems and instrumentation resulting from Licensee's response to the NUREG-0737 requirements. Licensees were requested to submit proposed Technical Specification revisions for these requirements within 90 days of receipt of the November 1, 1983 letter.

Attached are Wisconsin Electric's proposed Technical Specification changes for these NUREG-0737 requirements. The following discussion addresses each of the items listed in Enclosure 1 to Generic Letter 83-37:

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,Mr. H. R.-Denton~

- February 29, 1984

1. Reactor Coolant System Vents

'The suggestedLlimiting conditions for operation have been added to Specification 15.3.1. Surveillance requirements for these valves will be-included in our

.ASME Section XI pump and valve inservi ce testi ng program. An. amendment to our program description will be'Provided.

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2. Post-Accident Sampling and' Analysis of Plant Effluents As suggestedi by the generic letter, we have referenced the program for' post-accident sampling and analysis in Section;15.'6.9 ofethe'adminiatrative controls section of_the' Technical Specifications. Maintenance of-the sampling and analysis- equipment is covered in the normal 21 plant-wide maintenance program.

3. Noble Gas' Effluent Monitoring Licensee's submittal dated October 7, 1983 included revised requirements for noble gas. effluent monitoring

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z under'the topic of radiological effluent technical specifications..~The steam line radiation monitors have been addressed in the revision to-Table 15.'3.5-5 in this submittal. Surveillance of the SA-ll monitors is included under Item 19 of Table 15.4.1-1, " Radiation

. Monitoring System".

4. Long-Term Auxiliary Feedwater System Evaluation

. Enhanced auxiliary feedwater-system specifications were issued by<the'NRC onl September 25, 1982 with License Amendments 62'and 67 for. Point Beach Nuclear Plant, Units 1.and 2, respectively.

5. .Contailnment Post-Accident-Monitors for Pressure, tjater Level, Hydrogen, and Radiation Table 15.3.5-5 has been revised to include suitable limiting conditions for operation for.these systems.

' Surveillance intervals and requirements'have been

-included in. Table 15.4.1-1.

'6. Instrumentation for' Detection of Inadequate Core Cooling Specifications addressing action-statements for the reactor vessel fluid level system and the in-core thermocouples have been included it. Table.15.3.5-5.

Surveillance intervals are included in Table 15.4.1-1.

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Mr.EH. R. Denton- February 29, 1984 7.. Control Room Habitability Requirements

. The Point Beach Technical ~ Specifications include

' limiting conditions for operation and surveillance requirements for the control room emergency filtration in Sections 15.3.12 and 15.4.11, respectively.

No. revision to these sections are necessary. Because there.is:no significant chlorine storage on site, there is~no necessity'for chlorine detection systems.

Accordingly, the' Specifications for chlorine detection systems are not applicable.

Although we:are: proposing these specification changes at this-time in order,to comply with:the schedule of Generic r

Letter 83-37, we must~. point out~that', as discussed in our letters dated . June '16, August '23, and November 29, 1983, the final placement of-. control room indications and' permanent power wiring forithis. instrumentation has not been completed. Our schedule -

for' completing these modifications is_ presently being reviewed.

A status' letter with our revised, schedule is being prepared and -

will'be sent to you shortly. 'Accordingly, we request'that these b ' specifications not be issued-until these systems have been fully

- completed. Please note that the changes. proposed with Item 2 are complete and may be issued at anytime.

As requested by 10 CFR 50.91(a) (1) , we have prepared Lthe following discussion concerning the issue of whether or not these proposed changes. involve any significant hazards considerations.

Such a determination must be made.using the standards and criteria specified in 10 CFR'50.92. The Nuclear' Regulatory Commission has

. provided' guidelines concerning the' application of these standards in 48-Federal Register 14870'.= Among the' examples cited in this reference that are considered as very likely not to involve a i

significant hazards consideration are changes that constitute additional limitations or restrictions not previously contained in Lthe1 specifications. - Since these: proposed changes constitute'such additional limitations, we believe these proposed revisions to the Technical Specifications do not involve significant hazards considerations.

. _In accordance withLthe': schedule of fees for reactor (facilityllicense amendments.as: listed'in 10 CFR.170.22, Licensee 1 has enclosed a' check in.the amount of $4,400 for'the applicable

's 1 license : amendment . approval fee. This_ amount represents the prescribed fees ' for a Class III approval for ' the Point ' Beach Unit 1 s_'

license and a class.I, or duplicate, approval fee for Point Beach Unit 2.. Our fee determination is based on the fact that the

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Mr. H.-R. Denton February 29, 1984 acceptability for these issues has been clearly identified by NRC positions (NUREG-0737 and Generic Letter 83-37) and, therefore, the issues do not involve an extensive NRC review.

As discussed above, we have also determined that these changes would not constitute a significant hazards consideration, and lastly.only a single safety issue, namely implementation of post-TMI modifications, is involved.

As further specified in the Commission's regulations, we are enclosing herewith three signed originals and, under separate cover, 40-copies of this license amendment application.

Please contact-us if you have any questions concerning this submittal.

Very truly yours, (k

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Vice President-Nuclear Power C. W. Fay Enclosure (Check No. 773181)

Copy to NRC Resident Inspector C. F. Riederer, PSCW Subscribed and sworn to before me this3(ydb. day of February 1984.

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Notary P%blic, State of Wisconsin My Commission expires / / ff Y.

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