ML20147D890

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Summary of 881202-03 Meeting W/Util,Inel & ORNL Re Status of Tech Spec Upgrade Program.Meeting Attendees & Listed Ref Encl
ML20147D890
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 01/12/1988
From: Heitner K
Office of Nuclear Reactor Regulation
To: Calvo J
Office of Nuclear Reactor Regulation
References
NUDOCS 8801200346
Download: ML20147D890 (14)
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{ t WASHING TON. D. C. 20555 g .8 January 12, 1988 Docket No. 50-267 MEMORANDUM FOR: Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects .

FROM: Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects

SUBJECT:

SUMMARY

OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC) ON TECHNICAL SPECIFICATION UPGRADE PROGRAM (TSUP) - DECEMBER 2-3, 1987.

On December 2 and 3, 1987 the NRC staff met with the staff of the Public Service Company of Colorado (PSC) at the Fort St. Vrain (FSV) site. Also in attendance were NRC contractors from Idaho National Engineering Laboratory (INEL) and Oak Ridge Nation Laboratory (ORNL). The purpose of this meeting was to discuss the status of the FSV-TSUP. Specifically, this meeting focused on areas related to cooling functions, electrical systems and the overall progress and schedule.

The meeting attendees are listed in Enclosure 1. References are listed in Enclosure 2.

A proposed schedule for the completion of the TUSP effort, sent by NRC to to PSC (Ref. 1) was discussed and modified at this meeting. A review of the proposed PSC revised draft technical specifications and discussions of NRC comments (Ref.

2&3) was accomplished during this meeting. The PSC material (Ref. 4) was sent to NRC prior to the meeting. Additional NRC staff comments on the auxiliary electric power system (Enclosure 3) were also discussed. The new classification status for the material covered at this meeting are listed in the tables in Enclosure 4. They are subject to verification when PSC submits their final responses. for ease of reference the six classification categories are listed in Enclosure 5.

A teleconference is scheduled for January 8, 1988. During this teleconference PSC will cover those items noted in the tables in Enclosure 4. The next meeting on TUSP is projected for mid-Fedruary,1988.

The new dates for the schedule milestones are listed in Enclosure 6. Incorpo-rated in this schedule is an allowance for the 8th of January teleconference i resulte to be integrated into the PSC responses to the NRC (The PSC responses l are rescheduled from 1/15/88 to 2/1/88.) These changes will cause about a six week slip in the overall schedule. The TS release to PSC is now projected for November 30, 1988, eso1200346 080112 7 DR ADOCK 0500

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Other major items of note are:

1.~ The PSC-draf t of final TS modifications is projected for April 11, 1988. This PSC submittal will include highlighting and justification of all changes made in this final draft. Also, this draft will include all "C items" not-included in previous PSC submittals to NRC.

The draft will have been reviewed and approved by the FSV Plant Operations Review Committee.

2. PSC will supply revised versions of the license amendments that have been approved since the TSUP began (about a dozen amendments). The review cf these revisions will also be incorporated into the final TER, now scheduled for May 30, 1988.
3. PSC will submit a quality assurance plan that is being used to complete the final draft TS modification. This material will be used by the NRC Technical Specifications Branch in their review.

The staff noted that there were uncertainties in the review schedule to allow for TS Branch QA/QC review and the internal NRC legal review. The NRC staff offered comments on the format and contents of LC0 3.5.1.1 through LC0 3.5.5.

PSC will consider these comments in their redraft of these LCOs.

ITI Kenneth L. Heitner, Project Manager Project Directorate-IV Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc: See next page DISTRIBUTION Docket or Central File NRC PDR Local PDR PD4 Reading J. Calvo Project Manager CGC-Bethesda E. Jordan J. Partlow NRC Participants ACRS (10)

PD4 Plant File PD4/PM ')db }d K Heitner I /lWS$

~ . _ _ . _ _ _ . ~ _ _ _ _ _ _ - .__ . - - - _ _ - _ _ - _ _ _ _ . _ _ _ _,

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,I Mr. R. O. Williams, Jr.

Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Departinent of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201-0840 Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr. , Acting Manager GA Technologies, Inc. Nuclear Production Division Public Service Company of Colorado Post Office Box 85608 16805 Weld County Road 19-1/2 San Diego, California 92138 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division Public Service Company of Cdorado P. O. Box 840 16805 Weld County Road 19-1/2 Denver, Colorado 80201-0840 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker Public Service Company of Colorado P. O. Box 640 Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Commitment Control Program Public Service Company Building Room 900 Coordinator Public Service Company of Colorado 550 15th Street Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place '

999 18th Street, Suite 1300 Denver, Colorado 80202-2413

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Enc 1 c sar e 1 l

TSUP Meeting Attendees i Na rne Organi:ation Sism Chestnutt (B) PSC Lic ensing J.L. Lewi s (1) PSC Plant Engineering Jim Miller (1) NRC/NPR/TSB Chr i s Kirour a (1) LLNL/NRR Contractor David Moses (B) ORNL/NRR Contractor Joseoh Stachew (9) INEL/NRR Contr ac tor Loui s N. Rib (B) INEL Consultant /

NRR Contractor Men Heitner (B) NRC/NRR/PP-IV Mar t y Deniston (B) PSC Operations Davi d Alber stein (B) GA Technologies Bri an Dyck (B) PSC Lic ensing James Selan (1) PSC Licensing J.A. Capone (1) PSC Lic ensing M.H. Hol rnes (B) PSC Licensing Alan Udy (1) INEL/NRR Contractor (1) Attended rueeting on 12/2/87 (B) At tended rneeting on both 12/263/87

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3 Enclosure 2 i Referen::es

1. Mernor an dunis K. L. Hettner to J.A. Calvo, " Ann oun c ernen t of f or thc orning rneet i ng wi t h PSC 'c onc er ni ng FSV, Dec eneber 2-4, 1987, dat ed Novernber 13, 1987.

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2. Letter: K. L. Heitner (NRC) to R. O. Wi l l i arns , Jr . (PSC),

G-87131, " RAf s on Sa f ety-Relat ed Cooling Func t ions", dated Apri1 17, 1987.

3. Let t er : K. L. Heitner (NPC) to R. O. Wi 111 arns, Jr . (PSC),

G-87217, dated July 2, 1987.

h 4 Letter: H. L. Brey (PSC) to J. A. Calvo (NRC), P-87410, dat ed Novernber 19, 1987.

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Enclosure 3 s

FORT ST. VMIN TECHNICAL SPECIFICATION UPGRADE PROGRAM SECTION 3/4.8 - AUXILIARY ELECTRIC POWER SYS7.MS Meeting Date: December 2/3,1987 Items to be Discussed:

DRE

1. LCOs 3.8.1.lb.4 and 3.8.1.2b.4 both require 100 gallons of diesel lubricating oil to be present for operating conditions (2 diesel generator sets required to be operable) and shutdown (1 diesel generator set required to be operable) respectively. It is not clear whether the 100 gallons required is for each operable set or for comon storage. This should be clarified. /
2. Surveillance procedure 4.t.1.1.2e.5.b allows 60 seconds for the diesel generator sets to auto start and energize the essential buses. Surveillance procedure 4.8.1.1.2f allows 20 seconds to accelerate to 1200 rpm. We could find no basis for this time being greater than 15 seconds (Section 8.2.5.2 of the updated FSAR, Revision 5). These allowances should therefore be changed to 15 /

seconds.

3. Surveillance procedure 4.8.1.1.2e.8 calls for tests of the diesel generator sets at 21200 kW for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />. Surveillance procedure 4.8.1.1.2a.7 is similar for at least 60 minutes. Damage to the generators could occur when operating at greater than full continuous load, especially when considering possible instrument inaccuracies that could actually call for a greater than full load. Therefore, even though the STS has the same potential for generator damage, this requirement should be changed to a range (such as 1150 50 kW) with the load verified by instrumentation recently calibrated and of known accuracy, 1
4. Section 3/4.8.2 Action a, acknowledges that a battery equalizing

, charge can exceed 24 hourc; however, it docc not rectrict the length of the equalizing charge (said to be between 3 and 5 days) nor the frequency with which equalizing charges can be applied. Batteries must be maintained in a state of readiness, available for immediate use for events such as station blackout and for diesel generator controls and field flashing and bus load shedding and control (see basis on page 3/4 8-15). Therefore, the 5 day limit should be imposed, and an equalizing charge while operating should be made the exception rather than an everyday occurrence.

5. Section 3/4.8.2 Action b does not direct efforts towards restoring an inoperative battery charger untti the battery is declared inoperative. This is not acceptable. A dedicated battery charger should be required to be placed (returned) to service with the same expediency that a battery is (restore to OPERABl.E status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
6. In the December 18, 1986 meeting, it was stated that plant specific values for Table 4.8.2.1 would be provided, specifically for specific gravity and cell voltage. Other than specific gravity for Category A, there were no changes. We also nete that battery It is of different design fror batteries lA and 18. Therefore, separate values may be necessary. We could not find this itern addressed in the August 24, 1987 (P 87272) response.
7. (a) Section 4.8.2.lf, 'perforrance discharge tests' should be

'perfortnance discharge test'.

(b) On page 3/4.8 26, references to ' Table 4.8 2' should be

' Table 4.8.2-l'.

(c) On page 3/4.815, reference to 'any of the five off site sources' should be changed to be in agreement with 3.8.1.la.

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L (d) is it necessary to include operability of the main transformer in conjunction with capability of the VAT 7 (e) What is the resistance of the inter-rack connections for the batteries (4.8.2.lb.2 and 4.8.2.lc.3), and is there a reason this value should not be trended?

(f) is the 121.5 volts in surveillance requirement 4.8.2.la.2. with reference to cells that are jumped out, the individual cell voltage or both?

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Enclosure 4 e

CLASSIFICATION STAT'JS OF TSUP ITDiS-RESULTS OF.12/2-3/87 KTG. AT PSC NRC COMMENT NRC TENTATIVE COMMEh7S LC0f AGREEMENT ATTACHMENT f 1 TO P-87410 Primary Coolant loops and Coolant Cire.

3.4.1.1 A P.4-1,see note 1 below 3.4.1.2 Action 1 A P.4-6 Staff accepted deletion of prev. par.1 Basis Al P.4-7 B P.4-8 3.5.1.1(all) Al P.5-1 SR 4.5.1.1 Al P.5-1 incl. lid +

Action revisions 3.5.1.2 A P.5-3 Basis Al P.5-4 3.5.2.1 A P.5-7 SR 4.5.2.1 Al P.5-8 3.5.2.2 A P.5-9 Basis Al P.5-10 3.5.3.1 Al P.5-13 SR 4.5.3.1 Al P.5-13 SR 4.5.3.2 Al P.5-14 3.5.4.1 Action Al P.5-21 Basis A P.5-23 Al P.5-24 mods to 2nd

& 3rd par.

3.5.5 Al P.5-25 ACTION Af P.5-25 &5-26 SR 4.5.5.lc.2 Al P.5-26 SR 4.5.5.3c.1 Al P.5-28 SR 4.5.5 Basis Al P.5-29 3.6.2.1 Action Al P.6-18 8 6-19 3.6.2.2 Action a. Al P.6-21 3.6.3 Action Al P.6-25 Note 1: PSC considering mod. to allow loop recovery at 12% power.

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e NRC COMMENT PREVIOUS NRC TENTATIVE COMMENTS

  1. NRC AGREEMENT CLASS.

SECTION 3/4.8 AUI. ELECTRIC POWER SYSTDiS (ENCLOSURE f 3)

ITEM i 1 B 2 Al , D* PSC input for 1/8/88 telecon Re D* see note 1 below 3 Af,D 1/8/88 telecon-PSC to provide values re diesel 4 D Discuss during 1/8/88 telecon 5 Af 6 B,Af (Al re footnote #4) 1(a) A 7(b) A 7(c) Af 7(d) Af 7(e) D 7(f) D* Jim Miller will review, incl. in 1/8/88 call Additional Items:

1 Af A Farveil. for air s arting receivers 2 A f , D* A,D* Re attach.3 to P-87272. item 25c,D* re equalizing charge 3 D* Diesel fuel surveil.

4 LCO 3.8.1.la Eb Attach.f5,P-87272 5 3/4 8-21,28 Af Re ACM, attach.f6 P-87272 Attachment #2 to P-87410 Definitions ,

1.1-1,33 A LCO 3.7.1.lb A P.7-1 Basis Par.1 A P.7-2 re added phrase on HCA Par.2 A P.7-2 deleted par.

Pa r. 3 A P.7-3 deleted par. + addt'l discussion from p. 5-1 LCO 3.7.1.5 D P.7-12 SR 4.7.1.5 D P.7-13 LCO 3.7.1.6 D P.7-15 SR 4.7.1.6 D P.7-15

, LC' 3.7.1.7 A P.7-17 SR 4.7.1.7 A P.7-17 i BASIS A P.7-18 l LCO 3.7.5 l BASIS Al P.7-34 STE par.8 beyond

! P.7-35 3rd par. should reflect BQ L LCO 3.9.1 Al P.9.1 PSC 2/1/88 resp. ,

, disc. at next otg.

l Note !!D*-Tomlinson input te time to start-delete for PSV 7 ,

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e NRC COWENT PREVIOUS NRC TENTATIVE COMMF3TS LOO i CLASSIF. AGRED4ENT -

Attachment #3 to P-87410 PSC Response to NRC Comments (G-87131)

De f .1. 3 t A A P.1-7 Table 1.1f1 Af Af Re interlock classif.

Table 1.1f2 B B p.4 l 3.2f1 F F 3.2f2 F F 3.4f1 D*,B,B Al,B,B (change) 3.4f2 F Al F,Al 3.4f3,f4 D*,B,F 3,B F (change) 3.4f5 F F 3.4f6 A A 3/4.5 B B

3. 5.1.1 f 1 A A 3.5.1.1f2 A A 3.5.1f3 A A 3.5.1.lf4 A,B A,B 3.5.1.lf; A A 3.5.1.1f6 A A 3.5.1.1f7 i Al 3.5.1.1f8,9 AA AA 3.L.1.1f10 B B 3.5.1.1711 B B 3.5,1,1f12 A A 3.5.1.1f13 A A 3.5.1.1114 A A 3.5.1.1f15 3 B i 3.5.1.1f16 Al B (change) 3.5.1.1f17 B A #, B 3.5.1.1f18 A A 3.5.1.1f19 Al,F Ai,F

, 3.5.1.1f20 B B 3.5.1.lf21 A A 3.5.1.1f22 B B 3.5.1.lf23 F F

3. 5.1.1 f 24 B B 3.5.1.2fl.f3 Af,Af Af,Al 3.5.1.2f2 A A 3.5.1,2f4,f5 A,B A,B 3.6.2.1f1 B B 3.6.2.lf2 B B 3.6.2.1f3 B B 3.6.2.lf4 B B 3.6.2.lf5 B B 3.6.2.2fl f3 D 3 (change) 3.6.2.2f2 B B 3

4 NRC COMMENT PREVIOS NRC TENTATIVE COMMEh75 LCO # CLASS. AGREMEhT b.6.3f1 B,A A,B 3.6.3f2 B B 3.6.3f3 F F 3.7f1 B Af B.Af re ACM only 3.7f2 B B 3.7.1.1#1 Af,3 Af,B <

3.7.1.1f2 Al,D' A,A (change) 3.7.1.1f3 Al A (change) 3.7.1.lf4 F F 3.7.1.1f' B B 3.7.1.2 Al,B Af,B 3.7.1.5 A A 3.7.1.6 B B 3.7.3 B B 3.7.5 B B 3.7.8f1 Al Af 3.7.8f2 Al Af 3.7.8f3 F F 3.7.8f4 B B 3.9.1(Part 1) Af Al 3.9.1(Part 2) F F SR 4.5.1.1 B B Attachment #4 to P-87410 3.5.1.1f1 A A 3.5.1.lf2 A A 3.5.1.lf3 A A 3.5.1.lf4 Af Af 3.5.1.lf5 Al Af 3.5.i.2f1 A A 3.5.1.2f2 Af Af 3.5.1.2f3 A,B A,B 3.5.1.2f4 Al Af 3.5.1.2f5 A A 3.5.3.1f1 A A 3.5.3.1f2 A,B A,B 3.5.3.2f1 Al Al 3.5.3.2f2,3,4 A.A.A.B A.A.A B 3.5.4 Al Af 3.6.2.2#1 B B 3.6.2.2f2 Al Af 3.6.2.2f3 A F (change, handle in ISI) 3.6.2.2f4 A A 3.7.1.1 A,B A,B 3.7.1.6 A A 3.7.4.2 A A

Enclo sur e 5 The folle.ing is the Categorization of Elect ' cal Technical Specifications coteents transmitted to PSC by tre NRC in the referenced letters, G 87056 and G 87161, Categorizat':n symbols used are the same as used in previous meetings and corresp:tdence:

A - Incorporate comment as is A# - PSC action item '

B - No a:tien needed (resolved by discussion)

C - PSC to explain in proposed TSUP amendment safety evaluation O - PSC/NRC discussion needed to resolve D' 'NRC action item E - Outside TSUP scope - no further discussion planned F - Outside TSUP scope - further discussion possible.

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f Ene1osure 6 Propcsed Schedul + For TSUP C ornpl et ion ACTIVITY DUE DATE Subcatagories

1. 5/30/86 Cornraent s (INEL:T1-17)

PSC Response to RA!s 2/1/88 PSC draft of final TS Mod. 4/1/88 Separate INEL & ORNL TERs 4/30/88 i Integrated INEL h ORNL TER 5/30/88

2. Sec t ion 3/4.8 Corntnent s (INEL T1-18)

Updated PSC r esponse 2/1/88 Final TER 3/1/88

3. Cooling Function Corarnents (ORNL T-7)

PSC r esponse to cornruent s 12/23/07 Fi nal TER 2/15/88

4. PRA on DBA-2 (ORNL T-6)

Final TER 12/15/87 NRC Positicn 1/30/88 Major Mil estones to Task Coropl et ion INTEGRATED INEL L OF.NL TER 5/30/88 PERFORM INDEPENDENT AUDIT REVIEW OF

, PSC TS & UPDATE FSAR VS TER -START 6/6/88 TO 7/5/88 L

COMPLETE PESOLVING DIFFERENCES l IDENTIFIED BY AUDIT REVIEW 7/29/88 LETTER TO PSC TRANSMITTING TER/SER 8/26/88 l

PSC SUBMITS FINAL TS MOD. 9/23/88 l

NRC STAFF COMPLETES OC REVIEW OF f PSC FINAL TS MOD. 10//7/88 -

NRC ISSUES SHOLLY NOTICE 10/21/88 f

TS FOR PSC RELEASED 11/30/88 f

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