ML19332B089

Application to Amend Licenses DPR-24 & DPR-27,changing Tech Specs 15.1,15.3 & 15.6,re Limiting Conditions for Operations,Definitions of Operability & Administrative Structure

ML19332B089
Person / Time
Site:	Point Beach
Issue date:	09/19/1980
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML19332B090	List: ML19332B089 ML19332B091
References
TAC-43031, TAC-43032, NUDOCS 8009250249
Download: ML19332B089 (3)

Text

i WISCONSIN Electnc ma couraur 23! W. MICHIGAN. P.O. BOX 2046. MILWAUKEE, WI 53201 1

I Septerber 19, 1980 l

CERTIFIED MAIL Pr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. HUCLEAR REGULATORY cob 3ISSION Washington, D. C. 20555

Dear Mr. Denton:

DOCKET l'OS .50-26C AND 50-301 TECHNICA'L SPECIFICATION CHANGE REOUf5T NO. 64 LIh:ITING CO"DITIONS FOR OPERA.BILIEY, POINT BEACH UUCLEAR PLANT UNITS 1 AND 2 In accordance with Part 50.59 of Title 10 of the Code of Federal Regulations, Wisconsin Electric Power Company (Licensee) hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 to incorporate the following changes and additions to the Technical Specifications for the Point Beach Nuclear Plant, Units 1 and 2. These changes were requested by the Nuclear Regulatory Conrission in Mr. Darrell G. Eisenhut's letter to All Power Reactor Licensees dated April 10, 1980.

The attached proposed Technical Specification pages consist of a revised definition of operability and several new specifications addressing the limiting conditions for operations.

As discussed in Mr. Eisenhut's letter, these specifications require corrective action or plant shut-down if circumstances in excess of those permitted by the limiting conditions for operation should occur. As discussed in our letter dated May 16, 1980, our policy and practice of operation of the Point Beach Nuclear Plant have always been in accordance with the intent of these specifications.

We have modified the terminology utilized in your model specification to conform with our present specifications. We have also specified that when it becomes necessary to shut down the plant, three hours rather than one hour be permitted to get to the hot shut-down condition. This provides for a more appropriate ramping down in power of the unit for turbine operability considerations. Of course, 60002504@ 8

Mr. M. R. Denton September 19, 1980 if the specific conditions requiring shut-down involved significant safety-related equipment which was seriously degraded, this shut-down could be accomplished more rapidly, including, if necessary, an immediate reactor shut-down.

These specifications also address inoperability of safety-related systems solely due to failure of their emergency or normal power supplies. Again we have modified the NRC standard specifications to conform with the Point Beach Technical Specification format.

We have included a specification addressing the momentary loss of normal or emergency power which results in immediate corrective action in accordance with Table 15.3.5-2, " Instrument Operation Conditions for Reactor Trip". This specification provides that such an occurrence shall not be interpreted as causing a violation of the specifications concerning minimum operabic channels and minimum degree of redundancy as presented in Table 15.3.5-2.

The lack of this specification has resulted in many interpretation j i

disputes in the past and would serve to clarify the intent of the Table 15.3.5-2 instrumentation specifications.

We are also taking the opportunity of this license amendments application to request two administrative changes to the Point Beach Nuclear Plant Technical Specifications. The first involves the composition of the Manager's Supervisory Staff as specified in Item 15.6.5.2.2. We propose that the Reactor Engineer be added to the list of members. 'The second change concerns Specification 15.6.11, " Radiation Protection Program". During an NBC inspection, it was suggested that this specification could be changed to pravide more flexibility for exercising positive control over individuals entering or working in areas where radiation levels are greater than 100 mrem /hr, but less than 1000 mnem/hr. Licensee's review of the NRC Standardized Technical Specifications revealed that other options are available which provide appropriate admini-strative controls. These options have been adopted into the revised Specification 15.6.11, submitted.

Licensee has reviewed the requirements of 10 CPR Section 170.22 regarding the schedule of fees for facility license amendment approvals. It is our determination that this application is subject to one Class III fee, for the LCO's requested by the Commission as modified by the Licensee; one Class II fee, for the administrative changes discussed above; and one Class I fee, since this license amendments application is for two essentially identical units and is submitted as one request. Accordingly, we are providing herewith a check for the total mnendment approval fees of $5,600. ,

Mr. H. R. Denton September 19, 1980 As specified in the regulation, we have enclosed three signed originals and forty copies of this amendments application.

Please contact us if you have any questions regarding this submittal.

Very truly yours, O

• l Executive Vice President Sol Burstein Attachments (Check No. 512999)

Copy to NRC Resident Inspector Point Beach Nuclear Plant Subscribed and sworn to before me this 19th day of September, 1980.

(C1 GWAAD- 91&

Notary Public, State of Wisconsin My Commission expires Jr d / /97 V.

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