ML20235E095
| ML20235E095 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/21/1987 |
| From: | Heitner K NRC |
| To: | NRC |
| References | |
| NUDOCS 8709250479 | |
| Download: ML20235E095 (10) | |
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Subject:
Surntnar y o f August 25-26,1987 Meet 2 ng at Fort St. Vrain iFSV? tc di scuss NRC st af f corntnent s on FSV Technic al Spec i f i c at i on Upgrade Program (TSUP).
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1987 the NRC staf f met v,th t ne staf f of the Public On August 25 and 26, Service Cornpany of Colorado (PSC) at the FSV f acility. Also in attendence I
were NRC contractors f r om Idaho and Oak Pi r!ge Nat i onal Laboratory National Engineering Labor ator y (INEL)
(ORNL). The purpose of this rueeting was to discuss the status of the FSV TSUP. The rnecting attendees are listed in Enclosure 1.
The meeting agenda, l
which was followed fairly closely, i s attached as Enclosur e 2. A proposed i
schedule for the complet ion o f the TSUP effort, sent by NRC to PSC (Ref.1) was discussed and enodi fled at this meeting, A review of the proposed PSC responses to the NRC-RAIs (Requests f or Additional Information) was dis-of the meeting. The new cl assi fication status
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l cussed during the major part are listed by TS-LCOs in tables in Enclo-for these responses, by NRC, sure 5. The acceptance status will be veri fied uhen PSC formally submits future. The next meeting on TSUP was the draf t responses in the nearA meeting date and location will be l
projected to be in 6-8 weeks.
4 weeks. Mike Holmes suggested established by teleconf er ence in about about 11/15/87 or about two weeks af ter the PSC submission l
a date of responses to RAIs on the Cooling Functions.
l of their and the NRC contrac-The NRC sta f f has rnet previously with the PSC staff, tors, on the subject of TSUP (Ref er ences 2 and 3). These meetings were basec l (Reference 4) of the final draft of the prirnarily on the NRC sta f f' r eview As a result of these rneetings, FSV upgraded Technical Specifications (TS).
the NRC comrnents cont ained in Re f er ence 5 wer e r evi ewed and c at egor i zed into one of six categories (listed in e.g., r e f er ences 2 and 3). For ease of r e f er ence, they are noted in Enclosure 3, attached. Reference 5 sumenar a r ed the NRC/PSC rneet i ng of 12/18/86 and transmitted RAIs. Fol l owi ng resolutions that PSC subtni t t ed documentation of comrnent these rneet ings, t o NRC were reached at the previous meetings with NRC in a letter These includes Subsequent RAIs wer e sent to PSC by NRC. Electrical technical speci fi-(Reference).
RAls on the final draf t (1) References 7 & 8, Ref erence 9 transmitted RAIs on safety related cooling functier cations; (2)
D and 10 tr ansmi t ted RAls to PSC on c ategor y A#,
o t o PSC; and (3) Reference The PSC proposed responses to the RAIs D# i t erns (Defined in enclosur e 3).
formed the basis of the meeting ;
submitted in the abovementioned r e f er ences, with PSC on 8/25-26/87.
As the basis for the cornpletion of the TSUP r eview, Ken Heitner discused the NRC letter of 5/30/06," Comtnents on the Final Draft of the FSV Upgraded focus.
Technical Sp ec i f i c at i ons" (Ref.4). The progress of the TSUP review is
[
into a proposed review completion which were expanded The milestones for the first three line items in Fig 1 on four items, (Ref.1) are on schedule.
Task T-36 (ORNL), the 4th line item, on risk ~
schedule (Ref.1).
a s s e s srn e n t, should be compl et ed by mid-Sept ember. Ken responded to two 1987-1988 Proposed Schedul e (ref.1). The quest ions on rail est ones in Fi g. 2, first question involved the NPC independent audit review of the TER. Men DRAFT 1
4 m.-r 3
EFT l
explained that this was an NRC QA process under the guidance of the Technical Speci fic ations Br anch. The second question was on the de fini tion of the rnilestones activity calling for the PSC to certi fy that the final TS i
Mods conf or m wi th the PSAR.
Mr. M.H. Holmes (PSC) provided a preliminary response to NRR's proposed l
schedule in terms of Ken Heitner's request for a worst case estimate. Mi ke Holmes believes that they rnet the 8/30/87 mil estone on the PSC r esponse to Sect i on 3/48 cornrnent s. However, Mike sees an overall 4 rnonth slippage in the proposed schedule, shown in Fig.1. The slippage involves two mi l est on es. On the 5/30/06 Comments line, Mr. Holmes-projects the PSC response to RAIs f rorn the proposed 9/1/87 to 1/15/88.
On the Cooling Function Comments line, he projects PSC response to cornments from 7/15/87 Mike said that he understood that these slippages may cause the to 11/1/87.
rel ease of the TS to PSC to be delayed f rom 5/88 to 8/88.
However, he felt there was suf ficient time to irnplement the upgraded TS prior to plant that This can be done by working on the various activities in parallel, restart.
rather than sequent i al l y.
It is PSC stated objective to use the upgraded technical spec i fi c at i ons for operations following the fourth reactor re f ueling cycl e.
This activity appears to be slipping to a 12/1/88 plant shutdown and 1/30/89 plant I
startup. The r e fueling schedule call s for a shutdown of 61 days. This estimate may increase as a result of planning for speci fic activi ties.But,
if the shutddown period exceeds 90 days, oper ating FSV will no longer be ec onomi c al.
Nen Heitner asked PSC for a letter of ficially providing comments and con fi rmation of this schedul e. He also requested that PSC consider submit-ting par tial packages to minimize the effect of the apparent slippages.
Other i t erns highl ight ed dur ing the roeeting:
- 1. PSC provided NRC with a draft of a parallel activity to the TSUP, the PPS-Setpoint Overvicw. The dr af t information is included herein as.
This will be done as a separate licensing action, outside the TSUP.
- 3. PSC accepted an action item to provide NRC with a report in 3-6 soonths to cl ar i f y what interlocks are def eated (r e the Interlock Sequence as a result of a change in the position-of the (node switch. The area Switch) of NRC interest was especially directed to changes for startup and low power operation.
- 4. Throughout the discussion, in response to an RAI, PSC indicated the possibility of rnoving an i t em from the TS to the Fire Protection Plan. PSC should highlight those TSs in this category and clari fy their current position.
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p e. m 48 l
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- 5. Ken Heitner briefly described the status of the DBA-2 study by l
ORNL/SAIC. As soon as a draft copy of this study is available, Ken will j
copy into the PDR and send a copy to PSC.
place a J
and David Moses recommended that PSC consider a require-j
- 6. Ken Heitner operation one of the 12.5% condensate pumps be during power ment that This would provide assurance that FSV would avoid fuel damage
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op er abl e.
1 in the event of a lons of off-site power. X,3 y,g l
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assur e a good pr oduct for the TSUP. This draft will be reviewed with the TS Branch for the adequacy of the PSC approach.
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0 CLASSIFICATION STATUS OF TSUP ITEMS-RESULTS OF 8/25-26/87 KTG
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NRC COMMENTS TO' PSC LTR. NRC TENTATIVE PSC (G-87056 &
P-87272 AGREEMENT COMMENTS G-87161) LCOs NITACID4ENT f 1 (T0 P-87272)
D1 3.8.1.1 ACTIONS a.2 and a.4 B
B (Joe) 4.8.1.1.2.a5 D
A (Ken) 4.8.1.1.2c2 D*
D*(Ken)
Review TBD by Ed Tomlinson 4.8.1.1.2f A
B (Ken / Joe)
Table 4.8.1-1 Af A (Joe / Ken)
Fig.3.8.1-1 Af A (Joe) 3.8.2.1 Action A Af A,A,A(Dave)
PSC accepted and incorporated NRC suggestions per p.6, to P-87272 Attachment #2 to P-87272 (Electrical systems) 1 D
Af (Ken)
Transferred to PPS review 2
D B (Joe)
Cover in PPS submittal; covered -
by general operability rqmts.
3 D
Af (Ken) 4 D
B (Joe / Ken) 5.2 D
B (Joe / Ken) 5.6 & 11 D
B (Ken) 5.7 D
C (Ken) 5.8 D
B (Ken) 5.10 D
B (Ken) l 5.11 D
B (Ken) 5.13,14,15 D
D*
Review TDB by Ed Tomlinson 6.2 D
B (Joe) 6.4 D
A (Joe) 6.5 D
B (Ken) 6.c D
D* (Ken) 6.d D
B (Ken) 6.6 D
A 6.8 D
A DMFT
'c
I b'
I 1
NRC COMMFXT PSC LTR NRC TENTATIVE COMMENTS i
P-87272 AGREEMENT ATTACHMENT # 3 TO P-87272 I
l 1
B B (Ken) l 2
D,D A,B 3
D
.A (Dave / Ken) l l
4c D
B 5
D A
6.a.3 D
B i
DR;ff
^
9 D
A 10 D
A 11 D
A j
12 D
D' (Joe)
PSC to give more info.
i J
12e D
B (Joe)-
13 D
B (Joe) j i
14b D
A 15 D
B,A (Joe) 16 D
B,B (Joe) 17 D
D*D* (Ken)
No generic guidance available from NRC (STS) 18 D
A 19 D
A (Joe) 20 D
A l
j 21 D
A i
i 22 D
B i
l 23 D
A 24 D
A 25a D
B 25b D
A l
25c D
Af,D*
Expand-have to address DC bus (Note resolution refers to #17 above) 26 D
A 27 D
A 28f Al D
As per comment #17 28g D
B l
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XRC COMMENTS TO PSC LTR. NRC TENTATIVE COMMENTS I
PSC (G87131)
P-87272 AGRFlMENT Iros De f.1. 34 Al, F A
re Safe Shutdevn Cooling, FSAR clarification RAI-PO-TSUP*
Table 1.1#1 Al Af Table 1.1#2 B
B (Dave) re LCO 3.9.1 3.2f1 F.
F (Dave)
RAI-PO-TSUP' 3.2.2 F
F (Dave)
RAI-PO-TSUP*
3.4f1 A,B,B D*,B,B (Dave) PSC agreed to use.one 12.5%
condensate purp available for power operation i
3.4f2 B,B F Af Al re spec for tondensate pump operability 3.4f 3, f 4 B.B F D*,B,F D* re Circ Water System-Service Water System 3.4f5 F
F FSAR clarification, ' RAI-PO-TSUP*
3.4f6 A
A 3/4.5 B
B (Dave)
- 3. 5.1.1 # 1 Al A (Dave) 3.5.1.1 f 2 Af A (Dave)
- 3. 5.1 # 3 Al A (Dave)
- 3. 5.1.1 # 4 B,B
. A,B (Dave)
- 3. 5.1.1 f 5 Al A (Dave / Ken)
- 3. 5.1.1 # 6 A
A (Dave)
- 3. 5.1.1 # 7 Af Af (Ihve) 3. 5.1.1 # 8,9 A.Al A, A (Dave) 3.5.1.1#10 B
B (Dave / Ken)
Classification could change
- 3. 5.1.1 f11 B
B (Dave / Ken) 3.5,1,1f12 A
A (Dave / Ken) 3.5.1.1#13 A
A (Dave) 3.5.1.1114 A
A (Dave) 3.5.1.1#15 B
B (Dave)
- 3. 5.1.1 f 16 Al Al (Dave)
Pending review of small condensate pump TS
- 3. 5.1.1 f 17 B
B (Dave / Ken)
- 3. 5.1.1 f 18 A
A (Dave / Ken)
- 3. 5.1.1 f 19 Af,F Al,F (Dave)
PSAR clarification, RAI-PO-TSUP*
f 3.5.1.1#20 B
B (Ken Dave)
- 3. 5.1.1 f 21 Al A (Dava) 3.5.1.1f 22 B
B (Dave, h )
3 RIFT
- P.A1-PO-TSUP= RAI potentially outside of TSUP scope L
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NRC COMMENTS TO PSC 12 NRC TENTATIVE COMMENTS l
l PSC (G87131)
P-8727e AGREDfENT
- 3. 5.1. l f 23 F
F (Dave)-
See Note 3.5.1.1f 23 below 3.5.1.1724 B
B (Dave) l
- 3. 5.1.2 f 1,3 Af,Al Al,Al (Dave) i 3.5.1.2f 2 Af A (Dave) 3.5.1.2f4,5 A,B A,B (Dave) 3.6.2.1 f 1 B
B (Ken / Dave)~
FSAR Clarification; RAI-PO-TSUP 3.6.2.1#2 B
B (Ken / Dave) 3.6.2,173-B B (Dave / Ken) add explanation with ref. in writeup of P-87272 3.6.2.1#4 B
B (Dave)
- 3. 6. 2.1 #5 B
B (Dave) 3.6.2.2#1,3 D
D (Dave)
PSC to find ref.; could chan8e'to A 3.6.2.2f2 B
B (Dave) 3.6.3f1 B
'A,B (Dave)
'3.6~.3#2' B
B (Dave)
PSC to provide previous ref. on this issue 3.6.3#3 F
F FSAR Clarification, RAI-PO-TSUP 3.7#1 B,Af B, Af(Dave / Ken) Later, may move. Sect.3/4.7.6 (ACM comments
& 3/4.7.7 to Fire Protection only)
Program Plan 3.7#2 B
B (Ken)
Accept 11 days offsite storage j
supply, then can resupply.
3.7.1.lf1 Af,B A#,B (Ken) 3.7.1.1#2 Af,B A#,D* (Dave)
Later, discuss re TS on 12.5%
condensate purp.
3.7.1.113 Al Al 3.7.1.1f4 F
F (Dave)
Corrected in updated FSAR Rev. 5 l
3.7.1.1f5 B
B (Dave) 3.7.1.2 B (Rewrite), B,Al Psc to explicitly include Al these valves in SLRDIS TS i
3.7.1.5 A
A 3.7.1.6 B
B 3.7.3 B
B 3.7.5 B
B (Dave)
PSC to clarify PCRV contain-ment function in bases for LCOs 3.75 & 3.4.1 &
Appendix D in. upgraded FSAR i
Note 3.5.1.1f23: FSAR clarification; RAI-PO-TSUP, but FSAR Chap-
)
ter 14 analysis implies that this feature is part of the primary l
success path for accommodating loss of normal cooling transient-l TS may be needed.
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NRC COMMENTS TO PSC LTR NRC TENTATIVE COMMEFTS PSC(G87131)
P-87272 AGREEMENT 3.7.8#1 A
Al (Deve) 3.7.8#2 Al Al (Dave) n r]em 3.7.8f3 F
F y
~
3.7.8f4 B
B 3.9.1(Part 1)
Al Al (Dave)
't 3.9.1(Part 2)
F F (Dave)
B (Ken)
PSC' concludes that it has to rely on analysis; can't do a simulated test.
ENCLOSURE 2 TO P87272 NRC COMMENTS PREVIOUS NRC TENTATIVE TO PSC CLASS.*
AGREEMENT COMMENTS l
Table 1.0-1 Al B (Joe) re ISS switch; Ken rqstd a i
report in 3-6 months
)
SL 2.2.1-5 A,B C (Joe) i LCO 3.0 E
A (Ken) 3.1.1-1 Af A
3.1.3-4,-8 A
F (Ken / Dave) see basis for LCO 3.1.3 3.1.6-6 B
D 3.2.1-1 A
A (Ken) 3.3.2.3-3 A,D*
A 3.3.2.3-4 A#,D*
D*
new input from NRC staff to be requested l
3.5.4 B
A (Dave) 3.6.4-2 Al F (Dave / Ken)
PSC to document basis for past practice 3.7.2-4 B
A (Joe) 3.7.6.3-3 D*
D (Dave / Ken) possible move to Fire Protection Plan 3.7.8-4 Al A (Dave) 3.7.10-3 A
F (Dave) 3.9.1-2 Al Af,B (Joe) specific new TS for monitors 3.9.1-3 Af,P*
A (Joe) 6.3/6.4-1 D*
B (Ken) 6.5.1.6a A#
A,B (Joe)
$$3 6.5.1.7b D
B (Joe)'
UIL aj 6.9.1.2a D
Al (Joe)
NRC Action 3 Al Al SLRDIS valve should have a TS.
Reference SLRDIS analysis and any EQ recently put in FSAR.
- Based on NRC letters dated 10/7/86 and 12/1/86 1
pm t., b $
({Q j 7
r.
4 11 O ENCLOSURE 3 TO P-67272 (PSC responses to NRC Letter G-87131)
ItAI.
PSC LTR. NRC TENTATIVE DESIGNATOR P-87272 AGRED4ENT COMMENTS
- 3. 5.1.1 f 1 Al A (Dave)
(LCO 3.5.1.1a2) 3.5.1.1f2 Al A (Dave) re SR 4.5.1.lb (b.2-b 4);
new SR 4.5.1.lb2 3.5.1.1f 3 Al A (Dave)
(LCO 3.5.1.1, 4th page. basis) 3.5.1.1#4 B
Al Basis to be revised by PSC 3.5.1.1#5 Al Al (Dave)
PSC to rewrite basis of this TS '
- 3. 5.1.2 # 1 A
A (Daye) 3.5.1.2f 2 B
Al (Dave)
PSC to revise basis of this TS
- 3. 5,1,2f 3 A,B A,B (Dave) 3.5.1.2f4 Al Al (Dave)
PSC.to remove ref. to irrad.
fuel in all If0s where limits are not needed.
.J 3.5.1.2f 5 Af A (Dave)
Add new par. 3.0.5 defining calc. bulk core temp.
3.5.3.1#1 Al A (Dave) 3.5.3.lf2 A,B A,B (Dave) 3.5.3.2#1 Af Al (Dave / Ken) PSC to change TS to: orderly 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdewn and delete ref. to irrad. fuel.
3.5.3.2#2,3,4 Al,Af A, A, A,B (Dave)-
3.5.4 Al Al (Dave) change 10 min to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; re shutdown cooling 8 no ref.
to irrad. fuel.
f 3.6.2.2#1 B
B (Dave) 3.6.2.2f2 A#
A# (Dave) one loop of PCRV LCS must be operable or primary coolant flow be maintained when CBCT <760 deg.F' 3.6.2.2#3 B
A (Dave) 3.6.2.2#4 A#
A (Dave) 3.7.1.6 Af A (Dave) 3.7.4.2 Al A (Dave) 3.7.1.1 A,B A,B (Dave)
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