ML20211A646

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Proposed Tech Specs,Providing marked-up Pages for Proposed Changes 192 & 193
ML20211A646
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 09/18/1997
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20211A638 List:
References
NUDOCS 9709240320
Download: ML20211A646 (5)
v • d • e


Text

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  • h Vermont Yardse Nuclear Power Corp.  ;

- Docke*: No.90-271 ilVY 97107 M ARKFn.UP TECHNICAL SPECIFICATION PAGES FOR PROPOSED CHANGE 192 l i

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9709240320 970918 PDR ADOCK 05000271 P PDR; \

I W NPS I

. , Letter from L. A. Tremblay, Jr. (WNPC) to USNRC,

  • ' Supplemental Infomation to WNPC April 19, 1990 Response Regarding FROSSTCY-2 Fuel Perfomance Code,
  • BW 90-054, dated May 10, 1990 (Approved by NRC SER, dated September 24, 1992),

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,, ( Latter from L. A. Tremblay, Jr. (WNPC) to USNRC, ' Responses e i to Request for Additional Information on FROSSTEY-2 Fuel

  • r  ?# 5 Performance Code,* BW 91-024, dated March 6, 1991 (Approved I bfC i.

by NRC SER, dated September 24, 1992). I

$ {c .N Letter from L. A. Tremblay, Jr. (WNPC' to USNRC, 'LOCA-Related Responses to open Issues on F' JSSTEY-2 Fuel

$ Performance Code,

  • BW 92-29, dated
  • arch 27, 1992 (Approved I hv{8 .

by NRC SER, dated September 24, le .

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fu e4 5 Letter from L. A. Tremblay, Jr. .NRC) to USNRC, 'FROSSTEY- j d '- 2 Fuel Terformance Code - Vermont 'ankee Response to i

.'! [ '} Remaining Concerns,

  • BW 92-54, da 'd May 15, 1992 (Approved (g4 by NRC SER, dated September 24, 191 ).

A 1 4 y5 y Report, ' Loss-of-Coolant Accident Analysis for Vermont 1 'i# < Yankee Nuclear Power Station,* NEDO-21697, August 1977, as a dT amended (Approved by NRC SER, dated November 30, 1977).

..a Report, ' General Electric Standard Application for Reactor

'T e g3g ed a Fuel (CESTAPII),* NEDE-24011-P-A, CE Company Proprietary (the latest P.RC-approved version will be listed in the

h Report, General Electric Nuclear Energy, *BWR Owner's Group ct 1 Long-Term Solutions Licensing Methodology,* NEDO-31960, June 1991 (Approved by NRC SER, dated July 12, 1993).

Report, General Electric Nuclear Energy, 'BWR Owner's Group ,

Long-Term Solutions Licensing Methodology,' NEDO-31960, l Supplement 1, March 1992 (Approved by NRC SER, dated '

July 12, 1993).

The core operating limits shall be determined so that all applica*.21e limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic lim!ts, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The COLR, including I any mid-eycle revisions or supplements thereto, shall be l provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional i Administrator and Resident Inspector.

B. Reportable occurrences This section deleted. I s l C. Untoue R.eportino Recuirements l

1. Annual Radioactive Effluent Release Report
a. Within 90 days after January 1 of each year, a report shall be submitted covering the radioactive content of effluents released to unrestricted areas during the previous calendar year of operation.

l 1

Amendment No. M, 64, M, 444, 444, EM, +44, N 270

Wemont Yankee Nuclear Power Corp.

DxLit No. 50 27i BVY 97106 M ARKED-UP TECIINICAL SPECIFICATION PAGES FOR PROPOSED CilANGE 123 -

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. 3.13. ,L!MITING CONDITIONS FCR 4.13 SURVE!LLANCE REQUIREMENTS  ;

OPERATION , l

e. At least once  !

3 years, parti $er11y i open hose station valves to verify valve operability aM y,q and no blockage. ,JJ 4.w r D.' (H/ah/Preksuf el C0 7 System D. [idh/P/es4u7e1 C0 7 Syste

1. Except as speciffed in specification 3.13.D.2,
1. The in the CO2 c lestebocat=A vaultleed _4 ***O , ,

. JJ the CO2 systems located switchgear room

  • and '

in the cable v t, diesel ftre pump day

,,g tank room shall be w ..,4 switchgear to and ,

diesel fire pump day demonstrated operable.- l tank room shall be  ;

operable, whenever a. At least once per  ;

equipment in the area ,4j six months by protected by the system verifying each CO2 '

is required to be ,,,,i a A c"*11ndogsdoes not operable, a nsaan less than

e. *m*

45 90% of its initial

2. From and after the date q
  • ad Ji'6 du rge .

that the CO2 system in -

$ 1,tl ,"[ M

the cable vault or a sy,% b. At least once per switchgear room is -

% 18 months by .

inoperable, within one verifying that the hour a fire watch shall system, including be established to associated inspect the location at ventilation ,

least once every hour, dampers, will provided that the fire actuate detection system is automatically to a operable in accordance simulated actuation ,

with 3.13.A. If the signal.

fire detection system is also inoperable, c. At least once per within one hour a operating cycle a continuous fire watch flow path test shall be established shall be performed with backup fire to verify flow suppression equipment. through each Restore the CO2 system- nozzle.

to operable status within 14 days or 4,g sutsmit a report within g' #+

the next 30 days to the **** f*# 7 i Cossaission as specified J '1 * %') * *' T M O'-

in 6.7.C.2 outlining Con Ma t. 4 '

the cause of a s s ocMs4 M **-

inoperability and the w m k3 s., re6as ae s

' plans for restoring the na eW. te.e s A CO2 system to operable , p. gga ,

status.

% W.w ress%

.p 17o ga 3 i

Amendment No. M , G, 117 245

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  • IAEEE8  !

3.13 & 4.13_ FIRE. PROTECTION SYSTDis j On May 11, 1976, Vermont Yankee received a letter from the NRC requesting that an in-depth evaluation of the existing fire protection  ;

systems be performed using Stanch Technical Position (BTP) APCSB 9.5-1 i as a guide. Concurrent with this evaluation a fire hasards analysis of  ;

the entire plant complex was required. In an offort to clarify the OTP .

an Appendix A was subsequently issued to specifically address operating

-plants, Enclosed with this Appendix the NRC requested that proposed

-Technical specifications on f tre protection also be subesitted. The subject section 3.13/4.13 and the following specific bases are those specifications evolving from these efforts. l A. The smoke, heat and flame detectors provide the early warning fire detection capability necessary to detect problems in vital areas of -

the plant. surveillance requirements assure these sensors and-their associated instruments to be operable. When the equipment .

protected by the detectors is not required to be operable, .

.i specifications covering the sensors and instruments do not apply.. ,

l 3,C, The Vital. Fire suppression Water System, CO2 systems, sprinkler

- D, F, systems and foam- systems specifications = are provided to meet

, and pre-established levels of system operability in the event of a G fire. These systems provide the necessary protection to assure safe reactor shutdown. Periodic surveillance testing provides assurance that vital-fire suppression systems are operable.

E. Vital fire barrier penetration-fire seals are provided to assure that the fire resistance rating of barriers is not reduced by a penetration. . surveillance inspections shall be performed to insure -

'that the integrity of these seals is maintained.

The diesel ftre pusy has a design consumption rate of la gallons of fuel per hours therefore, 150 gallons provides for greater than  ;

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of operation. Additional fuel can be delivered in about one hour and additional fuel is on site. When the equipment protected by the ftre protection systems is not required to be _

operable, the specifications governing the fire protection system do not apply.

4 V N Tht. en a4 amh was4 aW+th s e r e..u low N wre.ce s 64 rm3n. +=e b Teth ers.d s e.3e stytc= N M at % t w ) .p gg, prov tae 6 6e ,s fG t c. t s a4 C.0 3 , gew4ih h e A t sus e. m%4 Me t A4*A ' J a&P3e t .n s e.w4ch4 teo w

3 16 e64 t.e 4 wse. ma *4h 6WP A 41. ]

(ivtO 7k tu. esd er ma4 .swt W 63 c r .ws . h Tw a nts A specifte. Mea et*We Nb tes.s sues. ap 17ce t a r) w,td

. pr. net Aa. -t*t-w w pe+ss.<v. % ***+ qah.a Jee t3n .

A A A t

- .. .i Amendment-No. H ,67:

-252

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