ML17292A156

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Discusses 951208 Application for Amend to License NPF-21 Re Conversion to Improved Ts.Lists Issues to Be Addressed as Part of Conversion
ML17292A156
Person / Time
Site: Columbia 
Issue date: 04/30/1996
From: Clifford J
NRC (Affiliation Not Assigned)
To: Parrish J
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
TAC-M94226, NUDOCS 9605020388
Download: ML17292A156 (14)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 1996 g o"-

39'7'r.

J.

V. Parrish (Hail Drop 1023)

Chief Executive Officer

. 3000 George Washington Way Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968

SUBJECT:

CONVERSION TO IHPROVED TECHNICAL SPECIFICATIONS (ITS) - WASHINGTON PUBLIC POWER SUPPLY SYSTEH NUCLEAR PROJECT NO.

2 (WNP-2)

(TAC NO. H94226)

Dear Hr. Parrish:

By letter dated December 8,

1995, you submitted an application for an amendment to Facility Operating License No. NPF-21 for WNP-2 to convert the current Technical Specifications (TS) in Appendix A of License No.

NPF-21 to Improved Technical Specifications (ITS) consistent with NUREG-1434 "Standard Technical Specifications General Electric Plants, BWR-6" (STS).

We have reviewed the proposed changes to determine those that constitute issues outs'ide the scope of the conversion process.

We intend to address as many of these as possible as part of the conversion.

However, several of these changes from the current TS requirements involve changes in the licensing basis which cannot be justified on the basis of the content of the improved STS and warrant particular plant-specific justification.

These issues are identified in the enclosure.

Certain of these issues may be difficult to resolve, and may unnecessarily delay timely completion of the conversion review.

These are:

Changes in the allowed outage times (AOTs) based on probabilistic risk analyses (PRA).

The review guidelines for PRA-based changes to AOTs are still being developed, and will not likely be resolved in time to incorporate these changes into the ITS.

(Items 13, 20, 26, and 28)

The extension in the surveillance interval for the airlock interlock to 24 months is a pending generic change to the STS.

If this change is resolved generically in the near term, it can be incorporated into the ITS for WNP-2.

Conversely, if the generic basis for the change is not resolved

soon, the change will have to be addressed with plant-specific justification or revert to the current TS requirement.

(Item 21)

The proposed changes to the voltage limits, frequency values and the number of required loss-of-power channels for the emergency electrical power system may require substantial staff review.

Consequently, because of resource and scheduling constraints, these changes in the licensing basis may not be resolved in time to incorporate the changes into the ITS.

(Items 17, 18 and 41).

0,'t0033 9605020388

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Hr. J.

V. Parrish You should advise the staff whether you want to withdraw these changes from the conversion and pursue them at a later date, or pursue these changes separate from but in parallel 'with the conversion, with corresponding changes to your amendment requ'est and,"ITS content:.'

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In addition, you have'arallel license"'amendment submittals, some of which are addressed in your cover letter for'this amendment application, that must converge with thTS -.prior f,to. it's issuance.,

Please-'inform us, as quickly as

possible, of 'all such-'xisting" or =planned submittals that are already reflected in or..that must-be incorporated in the'TS.

We will be sending you our questions arid 'comments in the next week and anticipate a conference)call and 'a'possible meeting in early Hay. If you have any questions, please.'contact,T.. Wambach, at (301) 415-1321.

Rf "Sincerely,'I I

k Original signed by S.

Bloom for:

James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

Beyond Conversion Issues cc w/encl:

See next page

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Docket 'File PUBLIC PDIV-2 Reading JRoe EGAl WBateman JClifford TWambach EPeyton ACRS

OGC, 015B18
KPerkins, RIV/WCFO
JDyer, RIV CGrimes l

DOCUMENT NAME:

NPF-21.WNP

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NAME Pe Son TWa bach:ye CGrimes Cs f DATE 4

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Hr. J.

V. Parrish You should advise the staff whether you want to withdraw these changes from the conversion and pursue them at a later date, or pursue these changes separate from but in parallel with the conversion, with corresponding changes to your amendment request and ITS content.

In addition, you have parallel license amendment submittals, some of which are addressed in your cover letter for this amendment application, that must converge with the ITS prior to its issuance.

Please inform us, as quickly as

possible, of all such existing or planned submittals that are already reflected in or that must be incorporated in the ITS.

We will be sending you our questions and comments in the.next week and anticipate a conference call and a possible meeting in early Hay. If you have any questions, please contact T.

Wambach at (301) 415-1321.

Sincerely, Original signed by S.

Bloom for:

James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

Beyond Conversion Issues cc w/encl:

See next page DISTRIBUTION:

Docket File PUBLIC PDIV-2 Reading JRoe EGAl WBateman

, JClifford TWambach EPeyton ACRS

OGC, 015B18 KPer kins, RIV/WCFO
JDyer, RIV CGrimes DOCUMENT NAME:

NPF-21. WNP

  • See Previous Concurrence OFC NAME DATE PDIV-2 LA MePon 4

96 P

-2 NRR:TSB*

TWa bach:

e 436 96 CGrimes 4 25 96 OFFICIAL RECORD COPY PD V-2 M

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Hr. J.

V. Parrish CC:

Hr.

G. 0. Smith WNP-2 Plant General Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352-0968 Chief Counsel (Hail Drop 396)

Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968 Hr. Frederick S. Adair, Chairman Energy Facility Site Evaluation Council P. 0.

Box 43172 Olympia, Mashington 98504-3172 Hr. D. A. Swank (Hail Drop PE20)

Regulatory and Industry Affairs Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352-0968 Hr. Paul R. Bemis (Hail Drop PE20)

Vice President, Nuclear Operations Washington Public Power Supply System P.O.

Box 968

Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower

& Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O.

Box 69

Prosser, Mashington 99350-0190 Hr.

R. C. Barr, Senior Resident Inspector U.S.

Nuclear Regulatory Commission P.O.

Box 69

Richland, Washington 99352-0968 H. H. Philips, Jr.,

Esq.

Winston

& Strawn 1400 i Street, N.M.

Washington, DC 20005-3502

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V RS ON ISSU S

Surveillance frequency changed from 18 months to 24 months for all surveillances normally performed at refueling outages.

LCO 3. 1.

and SR 3. 1.4 change to average scram time of 2x2 array of control rods with allowance for "slow" rods.

ACO...I d I t I

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t.i f 333 h

d 11 3

  • flow rate high.

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h 3

3 3

d ACTION f I p'1 Cddfp di ti monitors.

LCO 3.3.8. 1 - reduce number of required loss of voltage channels.

LCO 3.3.1.1 - revise STS ACTION for loss of one manual trip function to increase AOT from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SR 3.3. 1.2.5 note added which provides SR 3.0.1 exception for signal-noise ration.

LCO 3.3.3.1 -

PAM function SR frequencies.

Application of NEDO-30851-P-A to adopt a

6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT for required surveillances.

LCO 3.3.3.2 delayed entry into TS ACTION for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform surveillance.

LCO 3.3.6. 1 - delete ** Modes for reactor building exhaust radiation-high isolation signal for primary containment.

LCO 3.3.6. 1 deleted containment isolation functions.

LCO 3.3.6.2 - delete fuel handling sweep radiation monitor.

LCO 3.7. 1 - increased SW system AOT.

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hih temperature and area ventilation delta T.

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two radiation monitors is inoperable.

TCOI..T.I

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33dp vice CTS AOT of 7 days.

~CO 3.3.3.

11 h

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CTP 11 31 LCO 3.3.8.2 - all changes from CTS allowable values and new condition and applicability statements.

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19.

20.

21.

SR 3.4.8 Note added to Table to allow a channel to be inoperable for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> solely for performance of required SRs.

j CO 3.5. 1 extended AOTs for one low pressure ECCS subsystem, two low pressure ECCS subsystems, HPCS concurrent with one LPCI subsystem, and one ADS valve concurrent with one low pressure ECCS subsystem out of service.

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24 months.

22.

23.

C rre t TS 3 4

..6 deletion of entire specification for drywell and suppression chamber pressure.

Current TS 4.6.2.2.b - remove surveillance test of RHR pump recirculation flow thru RHR HX and suppression pool sparger to plant controlled document.

24.

25.

26.

LCO 3.6.2.3 add allowance of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore one RHR suppression pool cooling subsystem to OPERABLE with both inoperable.

SR 3.6.2.3. 2 - reduce required flow from 7450 gpm to 7100 gpm.

LCO 3.8.1 increase AOTs for DGs.

27.

SR 3.8.1 - increase start and load times for DGs from 10 to 15 seconds.

28.

29.

30.

LCO 3.8.2 increase in restoration completion time for DG-3 from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days.

SR 3.8.3.5 decrease frequency of water check in diesel oil from 31 days to 92 days.

SR 3.8.4.2 and 5 move resistance limits on connections to battery terminals to BASES.

31.

SR 3.8 4 6 reduce length of battery charger load test from 4 to 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

32.

S 3.8.4. 1 - reduce battery terminal voltage from 258 to 252 volts and from 129 to 126 volts.

33.

34.

~ttdd.d.

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dd d ltl' lpk 1

t 1

d 1

td" t 666 operabiity.

LCO 3.3.3. 1 JFD 0 8 - delete note to Condition C and Condition D for Hz monitors.

35.

LCO 3.3.4.2 - reduce frequency of reactor vessel pressure high ATWS-RPT function channel calibration from quarterly to 18 months.

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36.

LCO 3.4.7 change CRS PIV test pressure from 935 2 10 psig to 1035 pslg

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37.

~CO 3.

. 1 movement of power-.to-flow map from LCO to the COLR.

38.

~LCO 3.5.

change in pressure for AOS operability from 128 psig to 158 psig 39.

~LCO 3.

change in suppression pool 'level requirement in Modes q and 5 from 30 ft. 9 3/4 in. to 18 ft. 6 in.

40.

4.0 change in water level requirement for SFP from 605 ft 7,in. to 583 1 1/4 in.

41.

LCO 3.3.8. 1 - reduction in number of required loss of power channels.

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