NPL-99-0206, TS Change Request 212 to Licenses DPR-24 & DPR-27,updating References in TS to Reflect Relocation of Referenced Info in UFSAR

TS Change Request 212 to Licenses DPR-24 & DPR-27,updating References in TS to Reflect Relocation of Referenced Info in UFSAR

ML20205R667
Person / Time
Site:	Point Beach
Issue date:	04/12/1999
From:	Reddemann M WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20205R671	List: ML20205R674 NPL-99-0206, TS Change Request 212 to Licenses DPR-24 & DPR-27,updating References in TS to Reflect Relocation of Referenced Info in UFSAR
References
NPL-99-0206, NPL-99-206, NUDOCS 9904230264
Download: ML20205R667 (5)

Text

I e- .

MARK E. REDDEMANN ggg Siti Vics Presdent A WISCONSIN ENERGY COMPANY Point Beach Nuclear Plant i 6610Nucleaf Rd.

Two Rivers, WI S4241 Phone 920 7554527 NPL 99-0206 April 12,1999 10CFR50.4 '

10CFR50.90 l Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 i Washington, DC 20555 l

Ladies and Gentlemen:

DOCKETS 50-266 AND 50-301  ;

TECHNICAL SPECIFICATIONS CHANGE REQUEST 212 ADMINISTRATIVE CHANGES i POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2  ;

In accordance with the requirements of 10CFR50.90, Wisconsin Electric Power Company, licensee, hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27. The purpose of the amendments is to administratively update references in the Technical Specificat'ons. The update is  ;

necessary to reflect relocation of the referenced information in the updated Final Safety Analysis Report.

No Technical Specification requirement is altered by the requested changes.

Description of Affected Technical Specifications and Requested Change Technical Specification 15.3.5, Table 15.3.5-5," Instrument Operating Conditions For Post Accident Monitoring Instrumentation," defines the operability requirements for certain Post Accident Monitoring (PAM) instrumentation. A table note refers to the updated Final Safety Analysis Report (FSAR),

Table 7.7-2 for specific instmment loop designations.

In the June 1998 update to the Point Beach Nuclear Plant (PBNP) FSAR, the post-accident monitoring variables were relocated to FSAR Table 7.6-1. A change to the Technical Specifications is requested to -.

correct the note in Tecimical Specification Table 15.3.5-5 to refer to FSAR Table 7.6-1.

Technical Specification 15.4.6 defines required periodic tests for the emergency power system. l/

l Technical Specificaiion 15.4.6.A.2 requires testing to verify that the Emergency Diesel Generator starts and assumes the required load in accordance with the timing sequence in FSAR Section 8.2. This test ensures that the diesel starts and required engineered safeguards loads sequence as required by the

'Nck analyses and ensures that the starting transients do notjeopardize EDG operation. k'\

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99o423o264 990412 PDR ADOCK 05000266 P PDR ,

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NPL 99-0206 April 12,1999 Page 2 The June 1998 FSAR update relocated the information in FSAR Section 8.2 to FSAR Section 8.8. A change to the Technical Specifications is requested to reflect this relocation.

Attached are a Safety Evaluation, No Significant Hazards Determination, and mark-ups of the affected Tecimical Specifications indicating the requested changes.

We have determined that the proposed amendments are administrative only and do not involve a significant ha7xds consideration, authorize a significant change in the types or total amounts of any effluent released, or result in any significant increase in individual or cumulative occupational exposure.

Therefore, the proposed amendments meet the requirements of 10 CFR 51.22(c)(9) and an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared.

Please contact me if you have any questions or require additional information.

Sincerely,

&9 ark E. .ddemann ice Pre dent Point Beach Nuclear Plant Attachments cc: ' NRC Regional Administrator NRC Resident Inspector NRC Project Manager PSCW

.- Subcribed s and sworn before me en this*/ddayof gor // 1999.

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. ~ NoTad/Public, State ofWisconsin A/ary4./ dud /d_

My commission expires n /v/se/

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i NPL 99-02%

Attachment 1 Page1of2 DOCKETS 50-266 AND 50-301 SAFETY EVALUATION j

. TECHNICAL SPECIFICATIONS CHANGE REQUEST 212 ADMINISTRATIVE CHANGES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Wisconsin Electric Power Company, licensee, reques% amendments to Facility Operating Licenses {

DPR-24 and DPR-27 for the Point Beach Nuclea. , Units 1 and 2, respectively. The requested j amendments incorporate administrative changes t - Jechnical Specifications (TS). These changes are to references within the Technical Specification res n tents to information in the updated Final Safety Analysis Report (FSAR).' These changes are necessy ,o reflect relocation of the affected information within the FSAR.

An update, dated June 1998, was made to the FSAR in accordance with the requirements of 10CFR50.71(e). As part of this update, the FSAR was completely reformatted to better reflect present-day guidance for FSAR format. The reformatting will facilitate future updates of the document.

As a result of this update, existing information contained in the FSAR was consolidated and relocated.

In particular, information related to post-accident monitoring variables and Emergency Power Systems was relocated to other or new sections of the FSAR.

Technical Specification Table 15.3.5-5," Instrument Operating Conditions For Post Accident Monitoring Instrumentation," specifies operability requirements of certain post accident monitoring (PAM) instrumentation. A table note refers to FSAR Table 7.7-2 for the specific instrumentation channels for each of the table line items. Table 7.7-2 was replaced by FSAR Table 7.6-1," Post-Accident Monitoring Variables," with the June 1998 update. The new table more completely reflects instrumentation classified in accordance with Regulatory Guide 1.97 and is not limited to Technical Specification required instrumentation. The June 1998 FSAR update included table and figure cross-references to identify information relocated with the FSAR revision. This was done to ensure all appropriate requirements could continue to be located. No Technical Specification requirement or intent is being changed by the proposed amendments. The requested amendments are administrative only. ,

Technical Specification 15.4.6, " Emergency Power System Periodic Tests," defines requirements for testing of the emergency power system. - TS 15.4.6.A.2 requires, in part, demonstration that the i emergency diesel generators (EDG) will automatically start and assume required loads initiated by the interruption of normal AC power to emergency safety system buses. One required element of the test is the verification that the diesel generator starts and assumes the required loads in accordance with the timing sequence defined in FSAR Section 8.2. This section defines the requirements for sequencing of  ;

safety related loads required for accident mitigation. The timing requirements specified ensure the safety analysis requirements are met and also ensure the diesel generator is capable of assuming the required loads without challenging EDG operation. The June 1998 FSAR update relocated this  !

I information to FSAR Section 8.8. TS 15.4.6.A.2 is being modified to reflect this FSAR change.

-' NPL 99-0206 -

Attachment 1 Page 2 of 2 No change to the Emergency Power System test requirements is being made by this relocation and reflected change to the Technical Specifications. The change is administrative only.

As these changes are administrative only, do not affect the operatica cc testing of any structure system or component, or alter any Tecleical Specification requirement or interd, these changes have no adverse impact on the safe operation of PBNP or the health and safety . f the public.

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NPL 99-0206 Attachment 2 Page1of1 DOCKETS 50-266 AND 50-301 NO SIGNIFICANT HAZARD DETERMINATION TECHNICAL SPECIFICATIONS CHANGE REQUEST 212

-ADMINISTRATIVE CHANGES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with the requirements of 10CFR50.90, Wisconsin Electric Power Company, licensee, hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27. The purpose of the amendments is to administratively update references in the Technical Specifications. The update is necessary to reflect relocation of the referenced information in the updated Final Safety Analysis Report.

No Technical Specification requirement is altered by the requested changes.

. In accordance with the requirements of 10 CFR 50.91(a), Wisconsin Electric Power Company (Licensee) has evaluated the proposed changes against the standards of 10 CFR 50.92 and has determined that the operation of Point Beach Nuclear Plant, Units 1 and 2, in accordance with the

- proposed amendments does not present a significant hazards consideration. The analysis of the requirements of 10 CFR 50.92 and the basis for this conclusion follows:

1. Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments will not create a significant increase in the probability or consequences of an accident previously evaluated.

i The proposed amendment corrects references within the Technical Specification requirements such - i that they refer to the correct information in the updated Final Safety Analysis Report (FSAR). The references changed due to relocation of the information within the FSAR. The Technical Specification requirements and intent are not changed. Therefore, these changes are administrative only and do not change the design or operation of the Point Beach Nuclear Plant. Operation of PBNP in accordance with the proposed amendments cannot increase the probability or consequences

- of an accident previously evaluated.

2. Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments will not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes are administrative only and therefore do not materially change any requirements for the design or operation of PBNP. Therefore, operation in accordance with the proposed changes cannot create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Operation of the Point Beach Nuclear Plant in accordance with the proposed amendments does not l create a significant reduction in a margin of safety.'  !

i The proposed changes are administrative only; correcting references within the Technical Specification i requirements. No requirement on the operation or design of the facility is being changed. Therefore, there is no reduction in the margin of safety. )

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