ML18153B006

Proposed Tech Specs Changes Will Eliminate Remaining References to cycle-specific Parameters in Surry TS

ML18153B006
Person / Time
Site:	Surry
Issue date:	07/14/1994
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153B005	List: ML18153B004 ML18153B006
References
NUDOCS 9407190378
Download: ML18153B006 (7)

Text

• e Attachment 2 Technical Specifications Changes Surry Power Station 9407190378 940714 PDR ADOCK 05000280 P PDR

• 3.12 CONTROL ROD ASSEMBLIES AND POWER DISTRIBUTION LIMITS Applicability TS 3.12-1 Applies to the operation of the control rod assemblies and power distribution limits. Objective To ensure core subcriticality after a reactor trip, a limit on potential reactivity insertions from hypothetical control rod assembly ejection, and an acceptable core power distribution during power operation.

Specification A. Control Bank Insertion Limits 1. Whenever the reactor is critical, except for physics tests and control rod assembly surveillance testing, the shutdown control rod assemblies shall be fully withdrawn.

With a shutdown control rod assembly not fully withdrawn, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either fully withdraw the assembly or declare the assembly inoperable and apply Specification 3.12.C. 2. Whenever the reactor is critical, except for physics tests and control rod assembly surveillance testing, the full length control banks shall be inserted no further than the appropriate limit specified in the CORE OPERATING LIMITS REPORT. With a control bank inserted beyond the limit specified in the CORE OPERATING/

LIMITS REPORT, restore the control rod assembly bank to within its limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED POWER specified in the CORE OPERATING LIMITS REPORT, or place the I reactor in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 3. The Control Bank Insertion Limits shown in the CORE OPERATING LIMITS REPORT may be revised on the basis of physics calculations and physics data obtained during unit startup and subsequent operation, in accordance with the following:

Amendment Nos.

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• 0 £ LE 1~ 71-l IS F /6 Ui:2 FULL l~ITHDRA~/ii 225 '\ / ' / !J.4625,225) /' _/ 200 ....---' ./ '\ / " / ' ./ :,r -., ' / ' BANK C / *"' ./ I/ " 150 ' ' := (o.o. 151) ' ' ,__ ' ' ./ ' _/ ' -----* " ,, ' ,J<" ----/<. lOJ -**-;:z=::-*--* ----/ ---*--* / / / '\ -*--/ ' / 50 --/ / ,_ __ / ' -. :,,, I /-----(0.0, 23) -. -* --0 / ./ ,, ' ' '\ ' ( 1. 0' I ./ ./ ./ / " '\. ' ' " ' TS FIGU~~ 3.12-lA 01-06-88 ln!'"l--*--133 i ---./ ,, *-./ *------------*-*-. -~--.. ,.... . 0.0 0.2 0.4 0.6 0.8 . 0 FULLY Ir~SERTED FRA T C ION OF RAT ED PO ER w FIGURE 3.12-lA CONTROL BANK INSERTION LHHTS FOR 3-LOOP NORMAL OPERATIOU-WHT 1 Amendment Nos. 116 and l 16 IZ z 0 v, 0 Q.. c.. L.1..1 v, Q.. ::::::, 0 IX c..:, 0 0 IX LY 22 200 150 100 so 0 * ~ITH DRAWN ' / ./f * / TS FIGURE 3.12-13 01-06-88 ;;att:i.-1 0.4625,225)

., I ' ' / ' / ' ., -(1.0, 183) -'-' ./ ' ' .r I --_., ..r, BANK C _., ' ., _., ' .,,, ., ' / .. '~ ' ., --' ., ' _,,,,, :: (0.0, 151) ' / ' ., ' .,,, ' ., ' / ' / ' ., ,.,,, -.. _,r' ..L_ / *-/ --/ ---* / / -* / ' -----/ ' / ' ./ ' ., ' --/ ' --/ ' / ' " ' ' -.. -(0.0, 23) ' ' ,_ ' -------------' -*-a.a 0.2 0.4 0.6 0.3 1. FULLY INSERTED FRACTION OF RATED POWER FIGURE 3.12-lB CONTROL BANK rnsERTION LIMITS FOR NORMAL 3 LOOP OPE AA TION -UN IT 2 Amendment Nos. 116 and 116 IJ

• Attachment 3 Significant Hazards Consideration Determination Surry Power Station

• -Significant Hazards Considerations The proposed changes to Technical Specifications simply remove the remaining references to cycle-specific parameters in Technical Specification 3.12.A.2 and associated Technical Specification Figures 3.12-1 A and 1 B. These figures and the control bank insertion limits are presently specified in the Core Operating Limits Report (COLA). The NRG-approved methodologies presently listed in the Technical Specifications are used to calculate and evaluate the parameter limits presented in the COLR for each reload core. Virginia Electric and Power Company has reviewed the proposed Technical Specification changes against the criteria of 1 O CFR 50.92 and has concluded that the changes are administrative in nature and do not pose a significant hazards consideration.

Specifically, operation of Surry Power Station in accordance with the Technical Specification changes will not: 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The removal of the remaining reference to cycle-specific core operating limits and Technical Specification Figures 3.12-1 A and 1 B, from the Surry Technical Specifications has no influence or impact on the probability or consequences of any accident previously evaluated.

The proposed amendment is administrative in nature in that it corrects omissions from a previously approved amendment.

This change has no impact on actions to be taken when or if limits are exceeded as is required by the current Technical Specifications.

Each accident analysis addressed in the Surry UFSAR will be examined with respect to changes in cycle-dependent parameters, which are determined by application of NRG-approved reload design methodologies.

The impact of these parameter changes on transient results is then evaluated to ensure that the results remain bounded by respective transient analysis acceptance criteria.

This examination, which is performed per the requirements of 1 O CFR 50.59, ensures that future reloads will not involve an 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 accident previously evaluated.

The removal of the remaining reference to cycle-specific core operating limits and Technical Specification Figures 3.12-1 A and 1 B has no influence or impact, nor does it contribute in any Page 1 of 2 l

. . " * * ------------1 way to the probability or consequences of any accident previously evaluated.

No safety-related equipment, safety function, or plant operating characteristic will be altered as a result of the proposed changes. This cycle-specific variable (control bank insertion limits) is calculated using NRC approved methods, and the results are submittedto the NRC for information in accordance with Technical Specification 6.2. The Technical Specifications will continue to require operation within the required core operating limits, and appropriate actions will be taken when or if any of these limits are exceeded.

Therefore, the proposed amendment does not in any way create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Involve a significant reduction in a margin of safety. The margin of safety is not affected by this administrative change which removes the remaining reference to cycle-specific core operating limits and Technical Specification Figures 3.12-1A and 1 B from the Technical Specifications.

The margin of safety presently provided by current Technical Specifications remains unchanged.

Appropriate measures exist to control the values of these cycle-specific limits. The proposed amendment continues to require operation within the core limits which were developed from the NRG-approved reload design methodologies.

Further, the actions to be taken when or if limits are violated remain unchanged.

Development of limits for future reloads will continue to conform to those methods described in NRG-approved documentation.

In addition, each reload requires a 1 O CFR 50.59 safety review to assure that operation of the unit within the cycle-specific limits will not involve a reduction in any margin of safety. Therefore, the proposed changes are administrative in nature and do not impact the operation of Surry in a manner that involves a reduction in a margin of safety. Virginia Electric and Power Company concludes that the activities associated with these proposed Technical Specification changes satisfy the no significant hazards consideration criteria of 1 O CFR 50.92 and, accordingly, a no significant hazards consideration finding is justified.

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