GO2-84-032, Application for Amend to License NPF-21,revising Tech Specs Re intermediate-range Noble Gas Activity Monitor,Lpci Sys Injection Permissive,Containment Isolation for Fluid Sys & Diesel Engine Warmup Period
| ML17277B279 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/20/1984 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17277B280 | List: |
| References | |
| GO2-84-032, GO2-84-32, NUDOCS 8401310027 | |
| Download: ML17277B279 (10) | |
Text
REGULATORY ~ORMATION DISTRIBUTION SYS~R (RIDS)p ACCESSION NBR:8401310027 DOC,DATE: 84/01/20 NOTARIZED: YES DOCKET F4CIL:50-397 t4PPSS Nuclear Projecti Unit 2g 'I4ashington Public Powe 05000397 AUTH INANE AUTHOR AFFILIATION.
SORENSEN~G+C, Washington Public Power Supply System RECIP,NAME RECIPIENT AFFILIATION SCHHtENCERiA, Licensing Branch 2
SUBJECT! Application for amend to License NPF 21ir,evising Tech Specs re intermediate range noble gas activity monitoriLPCI sys injection permissiveicontainment isolation for fluid sys 8
diesel engine warmup period, DISTRIBUTION CODE:
8001S COPIES RECEIVED:LTR
.ENCL J SIZE!
t TITLE: Licensing Submittal:
-PSAR/FSAR Amdts 8 Related Correspondence'OTES'ECIPIENT ID CODE/NAME NRA/DL/ADL NRR L82 LA INTFRNAL~
ELD/HDS2 IE/DEPER/EPB 36 IE/DQASIP/QA821 NRR/DE/CEB 11.
NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRA/DHFS/HFEB40.
NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10, NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN5 EXTERNAL: ACRS 41 DMS/DSS (AMDTS)
LPDR 03 NSIC 05 COPIES LTTR ENCL 0
1-
"0 1
0 3
1 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 3
3 6
6 1
1 1
1 RECIPIENT ID 'CODF/NAME NRR L82 BC
'ULUCKtRe'1 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12 NRR/
AB 22 04 RM/DDAMI/MI8 BNL(AMDTS ONLY)
FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1
0 1
1 1
1 1
1 1
0 1
1 2
2 1
1 1
1 1
1 1
0 1
1 1
1 1
1 1
1 0
1 1
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 53 ENCL 46
,g hh e'h
>> i" II g
R ref
'R, W lli gt j,tiff'hg 'I fig g etg W'g~
g' g
~ et I tl g ge q,lg i t ij I tl.ltt.
r g
b tfll tv" b>>b f I (t fl' il g g gflb R R liiiltl,t Ij R>>'I II t g>> I $
ggf1 >> g'Ij f t If I'<~ R 1
'1 W
gg! y I>>g g',
i>> g I
g>> )>>
I'h
'gi )
Ig fg>>
F) f W
g gg i ggf a g A f.. ri J f gf J II g>> A, I q 3.<
R 1
WF)
W t jglfi tggJW,J F hf'Ig g I
t'g'4!I gg lj'1'll If()R tfD ! /l>>R l)g Rftht c>>
hl' e>>F e<<+>>>>e=
e>>ea
't
>>W' g'>>A leg
!i f,3;,
+)
)I Qp f ~I' I g jggt)>>')ll W>>'
9'f)'
f '"'J 4 fl i) II,'
>>I <>41; tj)J) 1'I 9
lych II eff gft I')Iw I' Ii I g c,lii g.b R II heetI
>> I
>>I'
/~It
', I
>>I 'jf R
R
, I. AI IW (Ilf t
II I'1 'tf, Itf i
ti lI Wll Itg
'i I II l,hl l'I WI '
l(
Fl l
F l * '.Ii>>
R F
R R
jt fib JK Rg) I,,I,W 1
j l
WXI., I, Wt tgfg g'I IW' t l
! ilii II )I 'I
, '1 II I, I, g, t I gg h
R R
R R
',,; tt,fggf j f,ill' I
til I b>>
I f
gtfft htt Jg W>>t IAI '>>,'
I 1 I ft ifI">>1 xR g, R
'f 5
j) 'bl
~ j g I J(
Wf1'f
!Ibg,ttf, 1
IW)hr II t,'fbg g 1
IW).
hh
(
II W
",,Rfil)I) i Ij f
- tIII,
!If g
j>>hjl, It, f
V)hi
'hi I
l 1
I lIjt'f',
g l,l 'tttt t>>',
'lf I
t t
,$ )I g)I o"
R I" 1':iI Ij 1 'J(
ji
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 January 20, 1984 G02-84-032 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. '0555
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO.
2 OPERATING LICENSE NPF-21, REQUEST FOR LICENSE AMENDMENT In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Washington Public Power Supply System (WPPSS) hereby requests revisions to the Technical Specifications, Appendix A to the subject license.
Enclosed are revised HNP.-2 technical specification pages 3/4 3-93, 3-94 and 3-95, 3/4 4-10, 3/4 6-22 and 6-31, 3/4 8-3, 3/4 8-l8, 3/4 9-3, and 6-7.
The following justification is provided in support of this amendment request:
o Pages 3/4 3-.93, 3-94, and 3-,95 The alarm functions for the intermediate range noble gas activity monitor. listed in table note 1 are not applicable in the WNP-2 design.
A distinct note 7 has.been added to accurately describe the channel functional test. required for the intermediate range monitor.
Since the intent of the surveillance is to verify channel operability only, in the interim until this change is approved, the Supply System will continue plant operation in support of the WNP-2 power ascension program and the intermediate range instruments as indicated in the attached changed pages.
f 84013100g7 Bqogp<>"
PDR ADOCK OS000397 P
)I I
J r'
A. Schwencer Page Two January 20, 1984 REQUEST FOR LICENSE AMENDMENT o
Page 3/4 4-10 Paragraphs b.
and d. should be deleted.
The LPCI system injection permissive at WNP-2 does not employ a valve differential pressure-low logic.
The logic employed senses reactor pressure.
The b.
and d. surveillance requirements were added to LaSalle Unit 1 Technical Specifications (page 3/4 4-8) for the period of time when the delta pressure logic system was in place.
Once the logic was modified, the surveillance requirements are no longer required.
The surveillance requirements, therefore, do not apply to WNP-2 since our logic was modified prior to issuance of our license.
In addition, the Supply System attended a meeting with the NRC/MEB on September 30 - October 1, 1981 and discussed these surveillance requirements (Ref. Question 849 of the meeting minutes and SER page A-12).
The minutes document our exception to the'urveillance requirements.
Drywell entry to perform this surveillance will require drywell purging.
As a result, the 90 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> limit on purging the drywell through the SGT system (LCO 3.6. 1.8) will, in all likeli-
- hood, be exceeded if paragraph
- b. remains.
o Pages 3/4 6-22 and 6-31 ANSI N271-1976, Containment Isolation Provisions for Fluid Systems, which is referenced by Regulatory Guide 1. 141, uses these values (12"/minute for Gates, 4"/minute for Globes) for valves 3>" to 12" in diameter.
For valves 3" in diameter or'less, ANSI-N271 valve closure times normally provided by standard commercial valve operators are adequate to limit as low as reasonably attainable the release of radioactivity from the containment.
The rationale behind this statement is reasonable.
Release of contaminants from failed fuel post-LOCA does not occur mechanis-
,tically until something on the order of a minute.
For a design basis accident, fuel uncovery does not occur for appproximately 30 seconds (Ref.
FSAR Figure 6.2-21a).
Peak clad temperatures do not occur for approximately 120 seconds (Ref.
FSAR Figure
,6.3-23).
A basis for accepting containment isolation valve closure times up.to one minute is that core inventory due to failed fuel is not present within that time interval.
Therefore, valve closure times up.to about one minute are considered adequate for 'containment isolation purposes-.
Since the valves indicated on Table 3.6.3-1 are 1",valves, the Haximum Isolation Time for those valves should be changed to.15 seconds.
~
~
I I I~
I N
I
'I ~
~ ~
~
~
~
~
A. Schwencer Page Three January 20, 1984 REQUEST FOR LICENSE AMENDMENT o
Page 3/4 8-3 LCO 3/4.8. 1, A. C. Sources, was revised by NRR/PSB to require a diesel engine prelube or warmup period prior to conducting the monthly surveil-lance tests.
Of the three diesels at MNP-2, only the DG 83 design pro-vides the capability to operate at a reduced speed for engine warmup.
A modification to the speed control circui try and a test procedure
'evision would be required to afford DG 81 and 82 the same capability.
The present LCO format can be adhered to but it should be noted that during the warmup period, the diesel is not in a standby status and will, therefore, not automatically respond to a LOCA signal as required by RG
- 1. 108, paragraph C.2.a.8.
The period of time required for an adequate warmup is dependant on various parameters (i.e., standby service water temperature, fuel oil characteristics, plant personnel performance
- time, etc.), but is conservatively estimated to take one hour per unit.
LCO 3/4.8; 1 action statements provide four (4) hours to complete the opera-bility surveillance and can be relied upon to require only a declaration of inoperability of the unit being tested since the unit can be warmed up and returned to standby in less than four (4) hours.
Surveillance testing would then continu'e in standby and with a prelubed diesel engine.
The increase in diesel reliability due to minimizing the harmful effects caused by cold starts is a significant improvement in the LCO.
The note referred to in paragraphs 4.8.1.1.2.a.4 and 5, however,
~re uires performance of a prelube period prior to testing.
This requirement may compromise plant safety if surveillance testing is required on a diesel generator due to another diesel generator being inoperative.
Conduct of the prelube period would then increase the number of emergency power supplies in an inoperable condition. It may, therefore, be preferable to perform a cold start test to retain the unit being tested in the standby mode.
This flexibilitycould be provided if the note read "may be preceded by an engine prelube period" versus "shall be".
The Supply System, therefore, requests that this change to LCO 3/4.8. 1 be considered.
There is an inherent problem with making technical specifications overly prescriptive because it is impractical to address all possible situations.
It is because of this need for flexibility that only the note in the LCO need be changed.
o Page 3/4 8-18
<<t Clarification.
Distribution panel DP-Sl-1F is the Division 1
125 - VDC critical switch, gear distribution panel and DP-Sl-1D is the Division 1 remote shutdown distribution panel.
The technical specification should be changed to reflect this. clarification.
A. Schwencer Page Four January 20, 1984 RE(UEST FOR LICENSE o
Page 3/4 9-3 To be operable by the OPERABLE definition in the technical specifi-
- cation, an SRH channel must have all attendant functions operable which include visual indication and an alarm function.
As presently
- stated, without change, the technical specification is redundant.
Additionally, an "audible indication" is currently required and has been interpreted by an NRC Region V inspector to require the type of audible indication employed by PWR vendors.
An audible indication of SRH operating levels is not a standard BWR design.
The present design alarms only to alert operators of increasing levels.
The
'ttached revised technical specification change clarifies the current techni cal speci ficati on.
o Page 6-7 The Nuclear Safety. Evaluation Group as described in the FSAR Appendix B response to NUREG 0737 item I.B.1.2 allowed members to meet ANSI qualifications as indicated in the attached draft Technical Specifi-cation.
This position was accepted in NUREG 0892, Safety Evaluation Report for WNP-2 dated Harch
- 1982, pages 13-22 and 13-23.
The Tech-nical Specifications should reflect the position as accepted in the Safety Evaluation Report.
Per 10 CFR 50.92, the Supply System has reviewed these changes and considers them to involve no significant hazard.
Additionally, the Supply System has evaluated this request in accordance with the criteria in 10 CFR 170.22 and has determined this request to be a Class II request involving several administrative changes of the Class II type.
Accordingly, a check for one thousand, two hundred dollars
($1,200) is enclosed in payment for this license amendment.
Should you have any questions with regard to this request, please contact Hr. P. L. Powell, Hanager, WNP-2 Licensing.
Very truly yours, G.
C.
S rensen, Hanager Regulatory Programs PLP/HRW/tmh Attachments cc:
R Auluck NRC WS Chin
- BPA D
Hoffman -
NRC AD Toth NRC Site
STATE OF WASHINGTON
)
County of Benton
)
g, A~~~ YlPF 2/-
Subject:
Pw I, G.
C.
SORENSEN, being duly sworn, subscribe to and say that I am the
- Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE /7 Jail.,
1984
- orensen, anager Regulatory Programs On this day personally appeared before me G.
C.
SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this l l day of
, 1984.
otary u
sc sn an or t e State of Washington Residing at
- j oei,duZ
,',l3Ti)!)Ifl2gf R3 3TATZ Aof098 to Qfflu03 odf
~~s I fsdf ysa has oJ'dnoadua,owe>a yfnb pried,W35)lAl)Z.3.Q,I YJRRUZ!l3l[00 3IJJUR VJTD'lIlHV'tUao>,ar~ssqoa0 yaofsfugeA,aepw.,'J aidf efuoexe ot ytnoNvs FFN evsd I fsdf;niece~) fasoifqqs edf,ldTZYZ yp %o faed odf of fsdf bos;goiogeao't erU be,reiver ov.-d I fsdf;dfso
.e~nf:ns fr oi ebs.'s afoe~;efsfa elf Weifed bns voifs.eo't'ai,egbeA<oo:)
~Z~F,
~
'm'e~lsgs
~
c ~Bafle"lo
~
~ i 3 a <<."n4a0 y~ofstugv'I of o',~w.3 e~ of 'ill!G.'l02.3
.:)
e;,~ e~ot~> b~wse~qs y~FFsooaweq ps'rdf o0 o>>'i)F~,'or6os i4n". foe,auafarri griiogowoT e f.~'Muoexe odv Fsubivr,'~@i,o;8 ed bffs ae
~l 9 "f f00 beeb dfts f.l!i eo'fi afd as e!3sa olU 590gfa 9'i Zsdf
.heooifnetr oiwedf aeaoqanq O'" F to ~h airlf I'sea bus bosd qs aebnu
~HUIS elf ao bns rir or 0'ardo Aofpflfdas.f to efsfZ fs gnibiae'1
>~~Lill:l)g~>/g~
QQ~;g<,
~ll<g)(ltll~