ML20234D907

From kanterella
Jump to navigation Jump to search
Requests Release of Encl Draft Document Re Summary of 871202-03 Meeting to NRC & Lpdrs
ML20234D907
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/31/1987
From: Heitner K
NRC
To:
NRC
References
NUDOCS 8801070284
Download: ML20234D907 (14)


Text

?

4 00chcN Mo. 50-'M 3

'( -

i Ndc  % ', Do c kc & R \er .072 P co Mannyse Fo Ae&st b ,o S u\oJ :

Prbchd AR 00 cu m m&

Tu a%eva s<A+ b o ea ar h her been p<uu,Jel %%

f u lol i % - v t c'e. Company o&

Cd omd o , A a co-d anc ca wh HRL OSC ce LdC h, e *l b e eeyeA %W yoa . Oro vt 8 t c.og t e r- To.

l h 4 RC onA Local P y3 R 's 4

's 8801070284 DR 871231

p. p ADOCM 05000267 PDR

, / 'o

~,,

UNITED STATES

!" n NUCLEAR REGULATORY COMMISSION

{' ,E WASHINGTON, D. C, 20555

  • s...../

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 results to be integrated into the PSC responses to the NRC (The PSC responses 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.

INT

1 l

. 1 DRAFT 1 Other major items of note are:

1. The PSC draft 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 licensee amendments that have been approved since the TSUP began (about a dozen amendments).

The review of these revisions will also be incorporated into the final TER, now scheduled for May 30, 1988.

l 3. PSC will submit a quality assurance plan that is being used to com-plete 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 LCO 3.5.1.1 through LCO 3.5.5.

PSC will consider these comments in their redraf t of these LCOs.

l 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 .g" J

Enc 1 csar e 1 );

TSUP Meeting Attendees Narn e . Organi:ation .

-),[ q

____ ____________  ; g-l Sam Chestnutt (B) PSC Licensing.

J.L. Lewi s (1) PSC Plant Engineering l- Jim Miller (1) NRC/NRR/TSB-Chri s Kimura (1) 'LLNL/NRR Contractor David' Moses (B) ORNL/NRR Contractor Joseph Stachew (B) INEL/NRR Contractor Loui s N. Rib (B) INEL Consultant /

NRR Contractor Ken Heitner (B) NRC/NRR/PP-IV Marty Deniston (B) PSC Operations David Alberstein (B) GA Technologies Bri an Dyck (B) PSC Licensing James Selan (1) PSC Licensing i J.A. Capone (1) PSC Licensing M.H. Holmes (B) PSC Licensing.

Alan Udy (1) INEL/NRR Contractor (1) Attended meeting on 12/2/87 (B) At t ended rneeting on both 12/2Ps3/87 i

i

. 1 Enc 1osure 2 References l

1. Mernor and urn: K. L. Heitner to J.A. Calve, " Announc ernen t I of f or thc orning rnesti ng wi t h PSC c onc erni ng FEV, Dec ernber 2-4, 1987, dat ed Novernber 13, 1987. ]
2. Letter: K. L. Heitner (NRC) to R. O. Wi 112 arns, Jr . (PSC), )

G-87131, "RAIs on Safety-Related Cool i ng Func t i ons", dat ed  !

Apri1 17, 1987. l 1

l

3. Let t er : K. L. Heitner (NRC) to R. O. Wi 111 arns, Jr . (PSC), i G-87217, dated July 2, 1987.

fl

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

l 1

JWT l

l l

l 4

l i

. . _ _ _ . _ _ _ _ _ _ l

)

Enclosure 3 l FORT ST. VRAIN TECHNICAL SPECIFICATION UPGRADE PROGRAM SECTION 3/4.8 - AUXILIARY ELECTRIC POWER SYSTEMS 1 1

Meeting Date: December 2/3,1987 Items to be Discussed:

1

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 >

common storage. This should be clarified. /

't

2. Surveillance procedure 4.8.1.1.2e.5.b allows 60 seconds for the diesel generator sets to auto-start and energize the essential i 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 sane 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. 4 1

l

d

4. Section 3/4.8.2 Action a, acknowledges that a battery equalizing charge can excoed 24 hourc; however, it docc not rectrict the icngth  !

of the equalizing charge (said to be between 3 and 5 days) nor the frequency with which equs11 ring charges can be applied. Batteries must be maintained in a state of readiness, available for immediate j 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.

b

5. Section 3/4.8.2 Action b does not direct efforts towards restoring an inoperative battery charger until the battery is declared j inoperative. This is not acceptable. A dedicated battery charger i should be required to be placed (returned) to service with the same expediency that a battery is (restore to OPERABLE 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 />).

i

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 l gravity and cell voltage. Other than specific gravity for Category A, there were no changes. We also note that battery IC is of different design from batteries 1A and 18. Therefore, separate values may be necessary. We could not find this item addressed in the August 24, 1987 (P 87272) response.

7. (a) Section 4.8.2.lf, ' performance discharge tests' should be

' performance discharge test'.

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

' Table 4.8.2 1' .

(c) On page 3/4.8-15, reference to 'any of the five off-site sources' should be changed to be in agreement with 3.8.1.la.

2 DMFT

7 DRJH l J

Is it necessary to include operability of the main t-insformer (d) in conjunction with capability of the UAT7 (e) What is the resistance of the inter-rack connections for the batteries (4.8.2.lb.2 and 4.8.2.1c.3), and is there a reason this value should not be trended?

l I

(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 1 voltage er both?- l DRAFT l

I i

I 3

l l

Enclosure 4 CLASSIFICATION STATUS OF TSUP. ITDiS-RESULTS OF 12/2-3/87 MTG. AT PSC

_ _ _ _ _ _ _ _ _ = -

NRC COMMENT NRC TENTATIVE COMMENTS LCOf AGREEMENT ATTACHMEhT f 1 TO P-87410 Primary Coolant Loops and Coolant Cire.

I 3.4.1.1 A P.4-1,see note -1 below a l 3.4.1.2 l Action 1 A P.4-6 Staff accepted ],

I deletion of prev. par.1 Basis Al P.4-7 B P.4-8 3.5.1.1(a11) Al P.5-1 SR 4.5.1.1 Al- P.5-1 incl. LC0 +

Action revisions nr) 9 -

3.5.1.2 Basis A

Ai P.5-3 P.5-4 gga 3.5.2.1 A P.5-7 SR 4.5.2.1 Al P.5-8 3.5.2.2 A P.5 Basis Al P.5-10 I 3.5.3.1 Af P.5-13  !

SR 4.5.3.1 Al P.5-13 1 SR 4.5.3.2 Al P.5-14 3.5.4.1 Action Al P 5-21  ;

Basis A P.5-23 l Al P.5-24 mods to 2nd -

& 3rd par.

3.5.5 Al P.5-25 i ACTION Al P.5-25 85-26 ,

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 & 6-19 3.6.2.2 Action a. Af P.6-21 3.6.3 Action Al P.6-25 t

Note 1: PSC considering mod. to allow loop recovery at 12% power.

I RAFT 1

I l

1

-_ --___-_-_-a

I

.g NRC COMMENT PREVIOUS NRC TENTATIVE COMMENTS i NRC AGREEMENT CIASS.

SECTION 3/4.8 AUX. ELECTRIC POWER SYSTEMS (ENCLOSl!RE f -3)

ITEM i

1. B 2 Af,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 I 5 Af 6 B,Af (Al re footnote #4). I

-7(a) A i 7(b) A I 7(c) Af )

7(d) Af i 7(e) D  ;

7(f) D* Jim Miller will review,. l incl. in 1/8/88 call Additional Items: 1 1 Af A Surveil, for air starting receivers 2 Al,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 D* Attach.f5,P-87272  !

5 3/4 8-21,28 Af Re ACM, attach.f6,P-87272 Attachment #2 to P-87410 I Definitions 1.1-1.37 A LCO 3.7.1.lb A P.7-1 I Basis Par.1 A P.7-2 re added phrase on MCA '

Par.2 A P.7-2 deleted par.

Par.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 l SR 4.7.1.6 D P.7-15 , i LCO 3.7.1.7 A P.7-17 SR 4.7.1.7 A P.7-17

'"y -

p BASIS A P.7-18 LCO 3.7.5 BASIS Al P.7-34 STB par.& beyond P.7-35 3rd par. should reflect EQ LCO 3.9.1 Al P.9.1 PSC 1/15/88 resp.,

disc. at next mtg.

Note 1:D*-Tomlinson input re time to start-delete for PSV 7 2

i 1

1 NRC COMMENT PREVIOUS NRC TENTATIVE COMMENTS LCO # CLASSIF. AGREFRENT

]

Attachment #3 to P-87410 PSC Response to NRC Comments (G-87131) l 1

Def.1.33 A Af P.1-7 Table 1.1#1 Af Al Re interlock classif.

Table 1.1f2 B B p.4 -I 3.2f1 F F )

3.2f2 F F 3.4f1 D*,B,B Af,B,B (change) 3.4f2 F,Af F,Al 3.4f3,f4 D*,B,F B,B,F (change) l 3.4#5 F F 3.4f6 A A 3/4.5 B B j 3.5.1.1#1 A A j

3.5.1.ll2 A A

{

3.5.1f3 A A i 3.5.1.1f4 A,B A,B j 3.5.1.155 A A j 3.5.1.lf6 A A i 3.5.1.1f7 Af Al l 3.5.1.1f8,9 A,A A,A 3.5.1.1710 B B 3.5.1.1f11 B B. '

3.5,1,1#12 A A 3.5.1.1f13 A A 3.5.1.1114 A A 3,5.1.1f15 B B 3.5.1.1f16 Af B (change) 3.5.1.1f17 B B 3.5.1.1f18 A A 3.5.1.1f19 Al,F Al,F 3.5.1.1f20 B B 3.5.1.1#21 A A 3.5.1.1f22 B B

, 3.5.1.1f23 F F

! 3.5.1.1f24 B B 3.5.1.2fl f 3 Al,Al Al,Al 3.5.1.2f2 A A

3. 5.1. 2 f 4, f 5 A,B A,B 3.6.2.1#1 B B 3.6.2.112 B B 3.6.2.1#3 B B f g, 3.6.2.174 B B lI 3.6.2.lf5 B B 3.6.2.2fl.f3 D B (change) 3.6.2.2f2 B B l

2-

e NRC COMMENT PREVIOS NRC TENTATIVE COMMENTS klYI LCO f CLASS. AGREEMENT 3.6.3f1 B,A A,B (change) 3.6.3f2 B B 3.6.3f3 F F 3.7f1 B,Af B,Af re ACM only 3.7f2 B B 3.7.1.1f1 Al,B Al,B 3.7.1.lf2 Al,D* A,A (change) 3.7.1.1f3 Al A (change) 3.7.1.lf4 F F 3.7.1.1f5 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 Af Af 3.7.8f2 Al Af 3.7.8f3 F F 3.7.8f4 B B 3.9.1(Part 1) Al 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 3.5.1.1f2 A A 3.5.1.173 A A 3.5.1.lf4 Al Af 3.5.1.1f5 Af Al 3.5.1.2f1 A A 3.5.1.2f2 Al Af 3.5.1.2f3 A,B A,B 3.5.1.2f4 Al Af 3.5.1.2f5 A A 3.5.3.171 A A 3.5.3.1f2 A,B AB 3.5.3.2f1 Al Af 3.5.3.2f2,3,4 A,A,A,B A,A,A,B 3.5.4 Al Af 3.6.2.2f1 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 Bf! aft

Enc'losure 5 The follcwing is the Categorization of Elect ' cal Technical Specifications comments 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 correspc.dence:

A - Incorporate Comment as is A# - PSC' action item-B - No action needed (resolved by discussion)

C - PSC to explain in proposed TSUP amendment safety evaluation D - 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.

l k .

2 l

i e

Enclosure 6  !

Proposed Schedule For TSUP Cornpl e t i on , , , ,


;y ACTIVITY DUE DATE N J at g I

Subcategories

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

PSC Response to RAIs 2/1/88 PSC dr af t of final TS Mod. 4/1/88 Separate INEL & ORNL TERs 4/30/88 Int egr at ed INEL & ORNL TER 5/30/88 l

2. Section 3/4.8 Comments (INEL:T1-18) l l Updated PSC response 2/1/88 i Final TER 3/1/88 l
3. Cooling Function Comments (ORNL:T-7)

PSC response to comments 12/23/87 Final TER 2/15/88' 4 PRA on DBA-2 (ORNL:T-6)

Final TER 12/15/87 NRC Position 1/30/88 Major Milestones to Task Completion 1

INTEGRATED INEL & ORNL TER 5/30/88 PERFORM INDEPENDENT AUDIT REVIEW OF  ;

PSC TS & UPDATE FSAR VS TER -START 6/6/88 TO 7/5/88 COMPLETE RESOLVING DIFFERENCES IDENTIFIED BY AUDIT REVIEW 7/29/88 j l

l LETTER TO PSC TRANSMITTING TER/SER 8/26/88 l

PSC SUBMITS FINAL TS MOD. 9/23/88 NRC STAFF COMPLETES OC REVIEW OF PSC FINAL TS MOD. 10//7/88 NRC ISSUES SHOLLY NOTICE 10/21/88 i I

TS FOR PSC RELEASED 11/30/88 Y]k(}

____--