ML20205J932

Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months

ML20205J932
Person / Time
Site:	Quad Cities
Issue date:	03/30/1999
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20205J926	List: ML20205J932 SVP-99-032, Application for Amend to License DPR-29,changing SR 4.6.E.2 to Allow one-time Extension of 18-month Requirement to Pressure Set Test or Replace One Half of MSSVs to Interval of 24 Months
References
NUDOCS 9904120268
Download: ML20205J932 (6)

Text

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i PRIMARY SYSTEM BOUNDARY Safety Valves 3/4.6.E 3.6 - LIMI MG CONDITIONS FOR OPERATION

- 4.6 - SURVEILLANCE REQUIREMENTS E. Safety Vi, *s E. Safety Valves The safety valve function of the 9 reactor 1. Deleted.

1 coolant system safety valves shall be 9 OPERABLE in accordance with the specified 2. At least once per 18[ months,1/2 of j i

code safety valve function lift settings

• the safety valves shall be removed, set established as: pressure tested and reinstalled or l

replaced with spares that have been i 1 safety valve" @1135 psig 1% previously set pressure tested and 2 safety valves @1240 psig 11% stored in accordance with 2 safety valves @1250 psig 11%

manufacturer's recommendations. At  !

4 safety valves @1260 psig 1% least once per 40 months, the safety valves shall be rotated such that all 9 safety valves are removed, set APPLtCABlV3 pressure tested and reinstalled or reL ;ced with spares that have been OPERATIONAL MODEls) 1, 2 and 3. previously set pressure tested and stored in accordance with ACTION: manufacturer's recommendations.

",. With the safety valve function of one or more of the above required safety valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in I COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Deleted.

l 1

T*ke S u ro *MIr ~a ode"s\ kss breu eshaded to 24 n As for 4ad I, escle if, malg . Tke gemsi.a s .i specda. N u 4.0.6 are a,ppta kle -

0 The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

b Target Rock combination safety / relief valve.

C.

AD CITIES - UNITS 1 & 2 3/4.6-7 Amendment Nos. 171 s 167 9904120268 990330 PDR ADOCK 05000254 P PDR -

ATTACIIMENT C Information Supporting a Finding of No Significant Ilazards SVP-99 032 (Page 1 of 2)

The Commission has provided standards for determining whether a significant Hazards consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license involves a no significant hazards consideration if op ration of the facility in accordance with the proposed amendment would not:

Involve a significant increase in the probability or consequences of an accident previously evaluated; or Create the possibility of a new or different kind of accident from any accident previously evaluated; or Involve a significant reduction in a margin of safety.

Comed proposes to amend Appendix A, Technical Specification SR 4.6.E of Facility Operating License DPR-29. The amendment request changes are consistent with the requirements of ASME Code Section XI,1989 edition, Subsection IWV 1000, w hich refers to ANSI /ASME OM (Part 10) which in turn refers to ANSI /ASME OM-1-1987; and NUREG 1482.

The determination that the criteria set forth in 10 CFR 50.92 are met for this amendment request is indicated below:

Does the change involve a sig Micant increbe in the probability or consequences of an accident previously evaluated?

The proposed changes request a one-time change to the surveillance requirement for the MSSVs and Target Rock. S/RV. The surveillance interval between MSSVs and Target Rock S/RV testing is not a precursor assumed in any previously analyzed accident.

Therefore, the probability of a previously evaluated accident has not been increased.

The proposed extension is consistent with the ASME Code requirement to test 20% of the sample population every 24 months with all of the valves in the sample group being tested every 60 months. The proposed changes are alsa consistent with NUREG 1433 Revision 1, and do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. Operating experience and excellent materiel condition of the MSSVs and Target Rock S/RV suppon the expectation that they will contmue to perform their iraended function. Therefore, the consequences of a previously evaluated accident have not been increased.

m

o 1 ATTACllMENT C Information Supporting a Finding of No Significant llazards SVP-99-032 (Page 2 of 2)

Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

No new equipment is required, nor will the MSSVs and Target Rock S/RV be operated in a different manner during the period of the extended surveillance interval. The proposed changes are consistent with NUREG 1433 Revision 1, requirements for safety valve surveillance intervals as well as the ASME Code requirements for testing safety valves.

Operating experience and superior materiel condition of the MSSVs and Target Rock S/RV support the expectation that they vcill continue to perform their intended function.

Therefore, the possibility of a new or different accident has not been increased.

Does the change involve a significant reduction in a margin of safety?

The proposed amendment repu.sents an extension to the current TS SRs that would otherwise be provided generically by the ASME Code. The proposed changes are also consistent with NUREG-1433, Revision 1, and do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. The proposed changes have been evaluated and found to be acceptable for use at Quad Cities Nuclear Power Station based on system safety analysis requirements and operational performance. The MSSVs and Target Rock S/RV provisions continue to be adequately maintained during plant operation. The proposed changes to the MSSVs and Target Rock S/RV surveillance interval do not significantly reduce existing plant safety  ;

margins since excellent materiel condition and acceptable surveillance test results support the expectation that no significant degradation will occur over the extended interval.

The proposed changes are based on NRC accepted provisions at otner operating plants that are applicable at Quad Cities Nuclear Power Station and maintain necessary levels of system or component reliability.

l The proposed amendment for Qued Cities Nuclear Power Station will not reduce the l availability of systems required to mitigate accident conditior;.

Therefore, these changes do not involve a significant reduction in the margin of safety.

Therefore, based upon the above evaluation, Comed has concluded that these changes involve no significant hazards consideration.

l

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4 ATTACHMENT D Information Supporting an E.mronmental Assessment SVP-99 032 (Page 1 of 1)

Comed has evaluated this proposed operating license amendment request against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. Comed has determined that this proposed license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) and as such, has determinea that no irreversible consequences exist in accordance with 10 CFR 50.92(b). l This determincion is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria:

(i) the amendment involves no significant hazards consideration.

As demonstrated in Attachment C, this proposed amendment does not involve any significant hazards consideration.

(ii) _ there is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.

As documented in Attachment C, there will be no change in the types or significant increase in the amounts of any effluents released offsite.

(iii) there is no significant increase in individual or cumulative occupational radiation exposure.

The proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant. Therefore, there will be no significant increase in individual or cumulative occupational radiation exposure resulting from this change.

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