ML20082E359

Proposed Tech Specs Re Change to Revise Operating Condition 2.c to Add Extension on Ice Condenser Surveillance 4.6.5.1.d to 951001

ML20082E359
Person / Time
Site:	Sequoyah
Issue date:	04/06/1995
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20082E353	List: ML20082E349 ML20082E359
References
NUDOCS 9504110204
Download: ML20082E359 (7)

Text

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h;;. . ;,y , 4 s: . ,. . "{. -:) ?. s h ENCLOSURE 1 PROPOSED-TECHNICAL SPECIFICATION (TS) CHANGE'

                                                         -SEQUOYAH NUCLEAR PLANT:(SON)' UNIT l'
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DOCKET NOS. 50-327 " l (TVA-SON-TS-95-09) r LIST OF AFFECTED PAGES ~' UNIT 1 OPERATING LICENSE PAGE 12 . 2 5 s I i f 4 4 j t 1 9504110204 950406-  %

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• 3- '(2) TVA shall maintain interim emergency support fa' cilities (Technical Support Center, Operations Support Center and the Emergency Operations Facility) until the final facilities are complete.

L' 1. Relief and Safetv Valve Test Reauirements (Section 22.2, ll.D.1) TVA shall conform to the results of the EPRI test program. .TVA shall provide documentation for qualifying (a) reactor coolant system relief and - safety valves, (b) piping and supports, and (c) block valves in accordance with the review schedule given in SECY 81-491 as approved by the - Commission. (24) Comollance with Reaulatory Guide 1.97 ~ TVA shallimplement modifications necessary to comply with Revision 2 of' Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following An' Accident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage. (25) Survelliance Interval Extension The performance interval for those surveillance requirements identified in the . licensee's request f3 or surveillance interval extension da'ted November 2,1994, /fA/O gpgj4,. shall be extended to October 1,1995, to coincide with the Cycle 7 refueling

                          # ffff        outage. The extended interval shall not exceed a total of 29.5 months for
                                      ' 18 month surveillance,48 months for 36-month surveillances, and 71.5 months for 54-month surveillances.
                                            ,                        f-                       F D. Exemptions from certain requirements of Appendices G end J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplements No.1. These exemptions are authorized by law and will not endanger life or property or the common defence and security and are otherwise in the public interest.                     j The exemptions are, therefore, hereby granted. The granting of these exemptions are authorized with the issuance of the License for Fuel Loading and Low Power Testing,                          ,

dated February 29,1980. The facility will operate, to the extent authorized herein, Act, l and the regulations of the Commission. Additional exemptions are listed in ' l AE . Attachment 1. E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the 'l Commission approved physical security, guard training and qualification, and safeguards l-contingency plans including amendments made pursuant to provisions of the l Miscellaneous Amendments and Search Requirements revision to 10 CFR 73.55 l (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). l The Safeguards Contingency Plan is incorporated into the Physical Security Plan. The l plans, which contain Safeguards information protected under 10 CFR 73.21, are l R77 entitled: "Sequoyah Physical Security Plan," with revisions submitted through l November 23,1987; and "Sequoyah Security Personnel Training and Qualification Plan," - l with revisions submitted through April 16,1987. Changes made in accordance with ' l 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. l January 3,1995 Amendment No.193

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ENCLOSURE 2 c-

                     - PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNIT 1 DOCKET NOS. 50-327 '              ,

(TVA-SON-TS-95-09) DESCRIPTION AND JUSTlFICATION FOR EXTENSION OF THE ICE CONDENSER SURVEILLANCE i 9

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• Descriotion of Chance TVA proposes to modify the Sequoyah ' Nuclear Plant (SON) Unit 1. technical
• specification (TS) to' revise License Condition 2.C.(25) to add a reference to this submittal that will allow'an extension for the ice condenser Surveillance .

Requirement (SR) 4.6.5.1.d.' This extension will support the Unit 1 Cycle 7 refueling outage schedule by allowing operation to October 1,1995. .This s schedule'is consistent with the extension date and surveillance intervals-approved by NRC in SON's License Condition 2.C.(25) that was approved'on

                 -January 3,1995.

Reason for Chanae m in the letter to NRC dated November 2,1994, TVA noted that additional surveillances were being evaluated that would exceed the allowable extension in September 1995. TVA has completed this evaluation and only ice- o condenser Surveillance 4.6.5._1.d could not be performed during power. operation and will require addition to the extension request. This extension request will extend the Surveillance 4.6.5.1.d interval approximately 4 weeke-beyond the 25 percent allowable extension provided by TS 4.0.2. The allowable extension provided by TS 4.0.2 will expire on September 5,1995. TVA performed ice weighing in the early stages of the~ Unit 1 Cycle 6 refuelin0 outage in June of 1993. After delays were incurred, TVA reperformed the' ice weighing in October 1993 to. support Cycle 7 operation. As indicated in the , November 2,1994 letter, TVA encountered additional obstacles in the

                 -successful return of Unit 1 to power. These problems, and the anticipated grid condition in the summertime, have caused TVA to resc'h edule the start of the Cycle 7 refueling ' outage to mid- to late-September 1995. : SON is not able to perform ice weighing on line and would require an unnecessary plant shutdown before October 1,-1995, without the proposed extension.

Justification for Chanaes SR _4.6.5.1.d prescribes an 18-month surveillance _ interval for weighing ice to . ensure that sufficient ice is present at the beginning of each refueling cycle such that at least 1,930,000 pounds of ice remains at the end of the fuel cycle. The 1,930,000-pound quantity (993 pounds on _ average per basket with 1944 baskets) is the analyzed safety limit value for the large break

               . loss-of coolant accident (LOCA) containment analysis presented in Final Safety Arialysis Report (FSAR) Section 6.2.1. The large break LOCA is the limiting accident for the design of the ice condenser and the amount of ice required.

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                  .lce sublimates with time during the operating _ cycle. ' As a consequence, ice is
                  - added to the bed during refueling outages to offset the anticipated sublimation.

Historically, sublimation rates are not uniform throughout the ice bed, with'. y higher. rates seen in the rows next to the containment shell and next to the crane wall. . For. outage dates.after mid-August, there is the possibility that the average basket weight for the 72 baskets in Row 1, Group 3, at a 95 percent-

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level of confidence,.will be less than the safety limit value of 993 pounds. This is the only row gMup that is projected to be below the safety limit.s Based on the current weighted average sublimation rate for'this row' group, the expected average weight of 979 pounds is pr'edicted for October.1,1995. It should be pointed out that, although the current FSAR analyzed safety limit is 1,930,000 pounds of ice, Westinghouse Electric Corporation also analyzed L the SON containment in WCAP-12455 for an ice weight of 1,880,000 pounds of ice. The peak calculated pressure for this case did not exceed 11.9 pounds per square in gauge (psig), which is below the design pressure of 12'psig. TVA submitted WCAP-12455 to NRC in TS Change Request 90-05 dated - January 12,'1990. The 1,880,000 pounds of ice translates into an average basket weight of approximately 968 pounds per basket. The average predicted as-found weight that is expected on October 1,1995, for Row 1, Group 3 is higher than this calculated limit. Thus, it can be concluded that the expected additional ice weight loss in the . ice condenser because of extending.the current fuel cycle until October 1,1995, does not represent a significant hazard to the health and safety of the plant or the public. Environmental imoact Evaluation The proposed change does not involve an unreviewed environmental question because operation of SON Unit 1 in accordance with this change would not:

1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or decisions of the Atomic Safety and Licensing Board.

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SON' that may have a significant environmentalimpact.

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a ENCLOSURE 3 'i PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNIT 1 , I DOCKET NOS. 50-327 l (TVA ISON-TS-95-09) - DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION i a b

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              ,f                                  Significant Hazards Evaluation .                                  .i

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H TVA has evaluated the proposed technical specification (TS) change' and has . i determined that it does not represent a significant hazards consideration based on

                 ; criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SQN) in accordance with the proposed amendment will not:                                          i 1.'   involve a significant increase in the probability or consequences of an accident             ;

previously evaluated. 1 The proposed change is temporary and allows a one-time extension of the' ice l 1 condenser Surveillance Requirement 4.6.5.1.d for Cycle 7 to allow surveillance testing to coincide with the seventh' refueling outage. The proposed '

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surveillance interval extension will not cause a significant reduction in system reliability nor affect the ability of the system to perform the design function. -t Current monitoring of plant conditions and continuation of the surveillance testing required during normal plant operation will continue to be performed to . ensure conformance with TS operability requirements. Therefore, this change -I does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any previously analyzed.

Extending the surveillance interval for the performance of ice condenser testing  !

                        - will not create the possibility of a new or different kind of accident. No change is required to any system configuration, plant equipmenti or analyses.

3. Involve a significant reduction in a margin of safety. ,

i The safety limits assumed in the accident analyses and the design function of - i the equipment required to mitigate the consequences of postulated accidents i will not be changed significantly. Existing analysis indicates that the potential reduction in ice weight resulting from the proposed extension will continue to maintain the maximum containment accident pressure below 12 pounds per square inch gauge. The ice condenser will continue to support accident mitigation functions although soma Row 1 baskets could drop slightly below the required 993-pound analysic limit. Therefore, the plant will be maintained with acceptable ice weights for accident mitigation and the proposed extension will not significantly reduce the margin of safety. 1

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