ML19331C604
| ML19331C604 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/21/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331C603 | List: |
| References | |
| NUDOCS 8008190110 | |
| Download: ML19331C604 (11) | |
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'o, UNITED STATES
'j NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555
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l YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. OPR-3 1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated September 24, 1979, (Proposed Change No.
167) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the aoolication, the provisions of the Act, and the rules and regulations of the Cornission; C.
There is reasonable assurance (i) that the activities authorized by the anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this acendment is in accordance with 10 CFR i
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
3008190 g4
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2.
Accordingly, Facility Operating License No. DPR-3 is hereby amended by changes to the Technical Specifications as indicated i
in the attachment to this license amendment, caragraph 2.C.(2),
j and the addition of a new paragraph 2.C.(5), to read as follows:
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(2) Technical Soecifications j
The Technical Specifications contained in Accendix A, as revised through Amendment No. 61, are hereby incoroorated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(5) Secondary Water Chemistry Monitorino Procran The licensee shall implement a secondary wa+er chemistry monitoring program to inhibit steam generator tube degra-t dation.
This program shall include:
I (a)
Identification of a sampling schedule for the critical parameters and control coints for these parameters; (b)
Identification of the crocedures used to measure the-values of the critical paraneters; I
(c)
Identification of crocess sampling points; (d) Procedures for the recording and management of data; j
(e) Procedures defining corrective actions for off control point chemistry conditions; and (f) A procedure identifying (a) the authority resconsible fcr the interpretation of the data, and (b) the sequence and timing of adninistrative events required to initiate corrective action.
3.
This license anendment is effective as of the date of its issuance.
F04 THE NUCLEAR REGitLAT Y C091IS 10N e;;;h; h{.
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Dennis M. Crutchfield, Chihf Ooerating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: JQly 21, 1980
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ATTACHMENT TO LICENSE AMENDMENT NO. 61 l
1 FACILITY OPERATING LICENSE NO. OPR-3 DOCKET NO. 50-29 l
Revise Appendix A Technical Specifications by removing the following pages and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of change. Over-leaf pages are included for document completeness.*
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l PAGES l
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3/4 7-10 3/4 7-11 3/4 7-12 i
B 3/4 7-3 i
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- Pages V, 3/4 7-9, and B 3/4 7-4
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS I
o SECTION PAGE r
i MAIN COOLANT ** SYSTEM (Continued)
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3/4.4.6 CHEMISTRY..............................................
3/4 4-12 j
3/4.4.7 SPECIFIC ACTIVITY......................................
3/4 4-15 3/4.4.8 PRESSURE / TEMPERATURE LIMITS l
Main Coolant System....................................
3/4 4-19 Pressurizer............................................
3/4 4-25 j
3/4.4.9
. STRUCTURAL INTEGRITY...................................
3/4 4-26 l
3/4.4.10 STEAM GENERATORS.......................................
3/4 4-32 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i 3/4.5.1 ACCUMULATOR............................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS........................................
3/4 5-3
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3/4.5.3 ECCS SUBSYSTEMS........................................
3/4 5-9 3/4.5.4 SAFETY INJECTION TANK..................................
3/4 5-12 l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..................................
3/4 6-1 Containment Leakage....................................
3/4 6-2 Containment Air Lock...................................
3/4 6-4 Internal Pressure......................................
3/4 6-5 A i r Temp e ra t u re........................................
3/4 6-6 Containment Vessel Structural Integrity................
3/4 6-7 Continuous Leak Monitoring System......................
3/4 6-8 3/4.6.2 CONTAINMENT ISOLATION VALVES...........................
3/4 6-9
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Amendment No.,4(, 52, 56 YANKEE-ROWE y
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCf REQUIREMENTS PAGE SECTION 3/4.6.3 COMBUSTIBLE GAS CONTROL Hydrogen Analyzer......................................
3/4 6-16 Hyd rog e n V e n t Sy s t em...................................
3/4 6-17 Atmosphere Reci rcula ti on System........................
3/4 6-18 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves..........................................
3/4 7-1 Emergency Boiler Feedwater System......................
3/4 7-5 Primary and Demineralized Water Storage Tanks..........
3/4 7-6 3/4 7-7 Activity...............................................
Turbine Generator Throttle and Centrol Valves..........
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........
3/4 7-13 3/4.7.3 PRIMARY PUMP SEAL HATER SYSTEM (Deleted)...............
3/4 7-14 3/4.7.4 SERV ICE WATER SYSTEtt (Del eted ).........................
3/4 7-16 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN.....
3/4 7-18 3/4.7.6 SEALED SOURCE CONTAMINATION............................
3/4 7-19 3/4.7.7 MASTE EFFLUENTS Radioactive Solid Waste................................
3/4 7-21 Radioactive Liquid Waste...............................
3/4 7-22 Radioactive Gasecus Waste..............................
3/4 7-23 3/4.7.8 ENV IRONMENT AL M0NITORI NG...............................
3/4 7-24 3/4.7.9 SHOCK SUPPRESSORS (SNUSBERS )...........................
2/4 7-27 3/4 7.10 FIRE SUPPRESSION SYSTEMS...............................
3/4 7-30 3/4 '7.11 PENET RAT I OM F I RE BARR I ERS..............................
3/4 7,-37 l
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YANKEE-ROWE VI Amendment No. A7, 52, ii.
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PLANT SYSTEMS l
TURBINE GENERATOR THROTTLE AND CONTROL VALVES LIMITING CONDITION FOR OPERATION l
3.7.1.5 Each turbine generator throttle and control valve shall be J
APPLICABILITY: MODES 1, 2 and 3.
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ACTION:
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MODES 1 - With one turbine generator throttle or control valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; Otherwise, be in at least HOT SHUTDOWN within the next 12 l
hours.
MODES 2 - With one turbine generator throttle or control valve inoperable, and 3 subsequent operation in MODES 1, 2 or 3 may proceed provided the inoperable valve is maintained closed; otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The provisions ai of Specification 3.0.4 are not applicable.
SURVEILtANCE REOUIREMENTS 4.7.1.5 Each turbine generator throttle and control valve that is open shall be demonstrated OPERABLE by:
a.
Cycling each valve through at least one complete cycle of full travel at least once per month, and b.
Verifying full closure within 2 seconds on any closure actuation signal whenever shutdown longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed in the previous 92 days.
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YANKEE-ROWE 3/4 7-9 AmendmentNo.,47[,52,SS
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BLANK (INTENTIONALLY) 4 I
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l YANKEE-ROWE 3/4 7-10 Amendment floS 1 l
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YANKEE-ROWE 3/4 7-11 Amendment No. 61 l
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BLANK YANKEE-ROWE 3/4 7-12 Amendment No. 6 1 1
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i PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that t
the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to sec-l ondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
The steam break accident is based upon a postulated release of the i
entire contents of the secondary system to the atmosphere using a site l
boundary dose limit Qf 1.31 rem for thyroid dose.
The limiting dose for this accident results from iodine in the secondary coolant. The reactor distribution of iodine isotopes with 15 failed fuel was used for this calculation.
1-131 is the dominant iso-tope because of its low MPC in air and because the other iodine isotopes have shorter half-lives and therefore cannot build up to significant concentrations in the secondary coolant, given the limitations on I
primarysystemleakrateanjactivity. The entire secondary system i
contains approximately 132m of water at standard conditions. One-tenth of the contained iodine is assumed to reach the site boundary, making allowance for plate-out and retention in water droplets.
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l 3/4.7.1.5 TURBINE GENERATOR THROTTLE AND CONTROL VALVES The OPERABILITY of the turbine generator throttle and control valvesensuresthateachsteamgeneratorwillbeiso}atedattheinstant of scram for a LOCA with an area smaller than 0.1 f t, as assumed in the
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accident analysis. The OPERABILITY of the turbine generator throttle i
and control valves within the closure times of the surveillance require-nents is consistent with the assumptions used in the accident analyses.
YANKEE-ROWE B 3/4 7-3 Amendment No. 61 l
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PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION
'The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations are based on a steam generator initial RTNDT plus 60'F and are sufficient to prevent brittle fracture.
3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM (Del eted) 3/4.7.4 SERVICE WATER SYSTEM (Deleted) 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN The OPERABILITY of the control room ventilation system emergency shutdown enhances the opportunity for the control room to remain habitable for operations personnel during and following accident conditions.
3/4.7.6 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed al.owable limits in the event of ingestion or inhalation of the source ma terial. The limitations on removable contamination for sources re-quiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakage of sources excluded from the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source mat-erial is inhaled or ingested.
i YANKEE-ROWE B 3/4 7-4 Amendment No.,47,,52', 56 s
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