ML20211A646
| 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) | |
Text
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Vermont Yardse Nuclear Power Corp.
- Docke*: No.90-271 ilVY 97107 M ARKFn.UP TECHNICAL SPECIFICATION PAGES FOR PROPOSED CHANGE 192 l
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9709240320 970918 PDR ADOCK 05000271 P
PDR; \\
W NPS 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 bfC by NRC SER, dated September 24, 1992).
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$ {c.N Letter from L. A. Tremblay, Jr. (WNPC' to USNRC, 'LOCA-Related Responses to open Issues on F' JSSTEY-2 Fuel hv{8 Performance Code,
- BW 92-29, dated
- arch 27, 1992 (Approved by NRC SER, dated September 24, le v
a 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 Report, ' Loss-of-Coolant Accident Analysis for Vermont y<
Yankee Nuclear Power Station,* NEDO-21697, August 1977, as 1 'i#dT amended (Approved by NRC SER, dated November 30, 1977).
a
..a e g3g Report, ' General Electric Standard Application for Reactor
'T ed Fuel (CESTAPII),* NEDE-24011-P-A, CE Company Proprietary a
- j l ;f (the latest P.RC-approved version will be listed in the COLR).
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Report, General Electric Nuclear Energy, *BWR Owner's Group 1
Long-Term Solutions Licensing Methodology,* NEDO-31960, ct 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, 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 any mid-eycle revisions or supplements thereto, shall be 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.
s C.
Untoue R.eportino Recuirements 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.
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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6 VYNPS l
3.13.,L!MITING CONDITIONS FCR 4.13 SURVE!LLANCE REQUIREMENTS OPERATION l
At least once 3 years, parti $er11y i
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open hose station valves to verify valve operability aM 4.w y,q and no blockage.
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[idh/P/es4u7e1 C0 D.' (H/ah/Preksuf el C0 7 Syste 7 System D.
stebocat=A _
1.
Except as speciffed in 1.
The CO2 specification 3.13.D.2, in the c le vaultleed 4 ***O,
. JJ the CO2 systems located switchgear room
- and in the cable v t,
diesel ftre pump day
,,g w..,4 switchgear to and tank room shall be 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 a nsaan less than
- e. *m 45 90% of its initial that the CO2 system in q $ 1,tl,"[ M
- ad Ji'6 du rge.
2.
From and after the date the cable vault or a sy,%
b.
At least once per 18 months by switchgear room is 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 **-
m k s., re6as ae s inoperability and the w
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' plans for restoring the na eW. te.e s A CO2 system to operable p.
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status.
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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, specifications covering the sensors and instruments do not apply..
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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.
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