NPL-97-0315, Suppl to TS Change Request 192 to Licenses DPR-24 & DPR-27, Modifying TS Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1

Suppl to TS Change Request 192 to Licenses DPR-24 & DPR-27, Modifying TS Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1

ML20140C902
Person / Time
Site:	Point Beach
Issue date:	06/03/1997
From:	Dante Johnson WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20140C907	List: ML20140C911 NPL-97-0315, Suppl to TS Change Request 192 to Licenses DPR-24 & DPR-27, Modifying TS Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1
References
RTR-NUREG-1431 NPL-97-0315, NPL-97-315, NUDOCS 9706100125
Download: ML20140C902 (4)

Text

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Wisconsin Electnc

', POWER COMPANY Point Beoch Nuclear Plant (414) 755-2321 6610 Nuclear Rd. Two Rivers. WI 54241 NPL 97-0315 10 CFR 50.4 10 CFR 50.90 June 3,1997 i

US NUCLEAR REGULATORY COMMISSION I Document Control Desk Mail Station Pl-137 Washington, DC 20555 Ladies / Gentlemen: I l

ROCKETS 50-266 AND 50-3.Q1 SUPPLEMENT TO TECHNICAL SPECIFICATIONS CllANGE REOUEST 192 POINT BEACH NUCI S AR PLANT. UNITS 1 AND 2 In a letter dated September 30,1996, Wisconsin Electric submitted Technical Specifications Change Request 192. This Technical Specifications change request proposes to modify Technical Specifications Section 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray" to incorporate allowed outage times similar to those contained in NUREG-1431, Revision 1, " Westinghouse Owner's Group Improved Standard Technical Specifications," and modify the operability requirements for the service water system. The proposed changes to Technical Specifications Section 15.3.7,

" Auxiliary Electrical Systems," r . so reflect the modified service water operability requirements.

The proposed change to Technica. Specifications Section 15.5.2, " Containment," modifies the heat removal capacity of the reactor containment air cooler units. Previous supplements to this Technical Specifications change request were provided in letters dated November 26,1996, December 12,1996, February 13,1997, March 5,1997, April 2,1997, April 16,1997, and May 9,1997.

This letter also provides supplemental information for Technical Specifications Change Request 192. This supplement proposes to modify the proposed Technical Specifications changes as described in Attachment 1. A supplemental safety evaluation and the revised edited Technical Specifications page for these proposed changes are also provided in Attachment I to this letter.

Attachment 2 contains supplemental information regarding the revised analysis of radiological r consequences of the loss of coolant accident. Attachment 3 contains additional information in i support of the radiological consequences of the loss of coolant accident. Attachment 4 contains I

supplemental and revised information for the containment integrity analysis and environmental /

qualification evaluation. ,,,

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4 NPL 97-0315 June 3,1997 Page 2 We have determined that the additional changes and information do not involve a significant hazards consideration, authorize a significant change in the types or total amounts of any effluent that may be released, or result in any significant increase in individual or cumulative occupational exposure. Therefore, we conclude that the proposed amendments meet the  !

requirements of 10 CFR 51.22(c)(9) and that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared. The conclusions of the original "No Significant Hazards" determinations for operation under the proposed Technical Specifications remain applicable.

We request exigent processing in accordance with 10 CFR 50.91(a)(6) of the entirety of the proposed Technical Specifications changes associated with this amendment request. The current plan for restart of Unit 2 from the current refueling outage is June 25,1997. It is estimated that approximately one week is needed after NRC approval of the amendment to allow for i implementation of revised Technical Specifications. This circumstance of exigency was not avoidable, based on the need to refine and revise the submittals due to emergent issues, principally control room dose analyses.

Please contact us if you have any questions.

Sincerely, Doug!m F. Johnson Manager-Regulatory Services and Licensing CAC/kmc Attaclunent cc: NRC Resident Inspector Subscribed and sworn before me on i NRC Regional Administrator this W day of Le. ,1997. l PSCW WA J Yr Notary @ublic, State of Wisconsinj

My commission expires V // 9 / / 9 y P 1

1 ATTACHMENT 1 TECHNICAL SPECIFICATIONS CHANGE REOUEST 192 SUPPLEMENTAL CHANGES AND SAFETY EVALUATION Introduction In a letter dated September 30,1996, Wisconsin Electric submitted Technical Specifications Change Request 192. This Technical Specifications change request proposes to modify Technical Specifications Section 15.3.3, " Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and Containment Spray" to incorporate allowed outage times similar to those contained in NUREG-1431, Revision 1, " Westinghouse Owner's Group Improved Standard Technical Specifications,"

and modify the operability requirements for the service water system. The proposed changes to Technical Specifications Section 15.3.7, " Auxiliary Electrical Systems," also reflect the modified service water operability requirements. The proposed change to Technical Specifications Section 15.5.2, " Containment," modifies the heat removal capacity of the reactor containment air cooler units. Supplements to this Technical Specifications change request were provided in letters dated November 26,1996, December 12,1996, February 13,1997, March 5,1997, April 2,1997, April 16,1997, and May 9,1997.

This supplement proposes additional Technical Specifications changes as follows:

1. Change Specification 15.3.12.2.b. to increase the minimum methyl iodide removal requirement from 90% to 99%. This change to the Technical Specifications for the control room emergency filtration establishes appropriate acceptance criteria for methyl iodide removal to provide assurance that the system will operate in j accordance with analysis inputs for determining operator exposure in the control  !

room.

2. Change the basis of Technical Specifications Section 15.4.11 to include the following statement: The charcoal adsorbent laboratory sample analysis is y performed in accordance with ASTM D3803-89, " Standard Test Method for Nuclear-Grade Activated Carbon."

Evaluation of these additional Technical Specifications changes is provided in the following safety evaluation. The "No Significant Hazards Consideration" provided in the original Technical Specifications change request was reviewed. The results of this review are provided in this supplemental information. The revised edited Technical Specifications are also provided as an attachment.

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i l Safety Evaluation This proposed change for the control room emergency filtration increases the minimum methyl iodide removal requirement from 90 to 99%. This increase preserves the accident

analysis assumption of 95% removal efficiency for control room habitability analyses.

Testing of the control room emergency filtration system is performed in accordance with Technical Specifications sections 15.3.12 and 15.4.11. The other testing requirements and l limiting conditions for operation described in these Technical Specifications remain valid and appropriate for this increase in the methyl iodide removal requirement. The inclusion of the test standard reference in the basis of Technical Specifications 15.4.11 does not change any current test requirement for Point Beach, because ASTM D3803-89 is the test standard that is currently used for Point Beach. l Review of"No Significant Hazards Consideration" l

The original"No Significant Hazards Consideration" provided with Technical Specifications change request 192 has been reviewed. The proposed modifications to this license amendment request do not alter any conclusions or the basis for these conclusions provided in the original"No Significant Hazards Consideration."

The only part of the original evaluation that is affected by these proposed modifications is the specific reference to the plant systems that are the subject of this license amendment  :

request. The first section of the original"No Significant Hazards Consideration" states:

i "This license amendment request proposes to change the limiting conditions for operation, action statements, allowable outage times, and design specifications for the Point Beach Nuclear Plant Technical Specifications associated with the containment accident fan coolers, service water equipment, and normal and emergency power supplies."  !

The proposed modification to this license amendment request proposes improvements to the limiting condition for operation associated with the control room emergency filtration operability requirement. As stated previously, these changes provide added assurance that the filtration system will operate in accordance with analysis inputs for determining operator exposure in the control room. Therefore, the conclusions and the basis for the conclusions in the previous "No Significant Hazards Consideration" are not changed.

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