ML19325D945
| ML19325D945 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/17/1989 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325D944 | List: |
| References | |
| NUDOCS 8910270212 | |
| Download: ML19325D945 (6) | |
Text
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UNITED STATES i
g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C,20665 P
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e YANKEE ATOMIC ELECTRIC COMPANY DOCKETNO.55-029 YANKEE NUCLEAR POWER STATION
.c ANENDMENT TO FACILITY CPERATING LICENSE
'n Amendment No. 125 Liesnse No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that-A.
The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated April 14, 1989 complies with the' standards and req)uirements 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 application, the provisions of the Act, and the rules and regulations of the Comission; -
C.
There is reesonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)-that such activities will be conducted in compliance with the Comnission's regulations set forth in 10 CFR Chapter.I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfieo.
2.
Accordingly, the license is emended by changes to the Technical Specifica-tions as indicated it: the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:
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(2) Technical Specifications l'
The Technical Specifications contaired in Appendix A, as revised L
through Amendment No.125, are hereby incorporated in the 11 cense.
l The licensee shall operate the facility in accordance with the Technical Specifications.
l l1 8910270212 091017 PDR ADOCK 05000029 i
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3.
This license amendment'is effective as of its date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION U Yh: h v
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Richard H. k'essman, Director o
Project' Directorate I-3 Division of Reactor Projects I/II' Office of Nuclear Reactor Regulation
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' Attachment-Changes to the Technical Specifications Date of Issuance:
October 17, 1989 f ::
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ATTACHMENT-TO LICENSE AMENDMENT N0.125 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET N0.50-029 i
Replace the following sages of the Appendix A Technical Specifications with
.the attached pages. T1e revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 7/4 7-1R 1/4 7-18 3/4 7-18a*
B 3/4 7-4 8 3/4 7-4
- Denotes.new page 1
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PLANT SYSTEMS 3/4;7.5' CONTROL ROOM EMERGENCY AIR CLEANING L.
LIMITING CONDITION FOR OPERATION l
3.7.5 The Control Room Emergency Air Cleaning System shall be OPERABLE.-
APPLICABILITY Modes'1, 2, 3,.and 4 ACTION a.
With the Control Room Emergency Air Cleaning System inoperable, except as a result.of one inoperable fan and motor set, rest' ore the system to OPERABLE status within 3-1/2 days or be in at least HOT STANDBY within the next 6' hours and in COLD SHUTDOWN within'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With one inoperable fan and motor set, restore the inoperable' fan and
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motor set to OPERABLE status within 7 days or be in at least HOT STANDBY
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within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30
- hours, SURVEILIANCE REOUIREMENTS E
4.7.5.1 At least once per 31 days:
a.
Initiate from the Control Room sud maintain for at least 15 minutes, for each fan and motor set Control Room Emergency Air Cleaning System flow through the HEPA filter and charcoal absorber.
b.
Manually shut down the Control Room unit ventilator, UV-2, f rom the Control Room and verify closure of the Control Roop Emergency Air l
Cleaning System Isolation Dampers A and B.
4.7.5.2 At least once per 18 months, manually close Control Room Fire L
Dampers B and E from the Control Room.
l 4.7.5.3 At least every 18 months and following painting, fire, or chemical L
release in any ventilation zone communicating with the system that could l.'
contaminate and impair the function of the HEPA filters or charcoal adsorbers, I
the Filter System shall be demonstrated OPERABLE by verifying that:
L a.
The results of the in-place cold DOP and halogenated hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show 199% DOP removal and 199% halogenated hydrocarbon removal.
b.
Within 31 days after removal that the results of laboratory carbon I
sample analysis performed at representative system flow rates shall show 199% radioactive methyl-iodine removal.
YANKEE-ROWE 3/4 7-18 Amendment Number 125
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r PIANT SYSTEMS j
EURVEff.flNCE REQUIREMENTS (continued)
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Recirculation Filter System flow rate is 3,000 cfm 110% during system operation.
d.
The pressure: drop.across the combined lprefilter and HEPA filter bank is 4 inches H O while operating at the system flows specified above.
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4.7.5.4 Following maintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested. Specifically:
Cold DOP t' sting shall be performed after each complete or partial e
a.
replacement of the HEPA filter bank.
b.
Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal filter bank.
c.
DOP and halogenated hydrocarbon test shall be performed following any significant modification to the filter housing that could have an adverse effect on the filter efficiency.
d.
An air distribution test demonstrating uniformity within 120%
across.the HEPA filters and charcoal adsorbers shall be performed 1 if the filter _ housing is modified such'that air distribution could be adversely affected.
4.7.5.5' The sample analysis of Specification 4.7.5.3.b shall be performed after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.
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YANKEE-ROWE 3/4 7-18a Amendment Number 125
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PLANT SYSTEMS RAEEE 4
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 NDT P us 600F and are sufficient to prevent l
on a steam generator initial RT brittle' fracture.
I 3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM (Deleted) 3/4.7.4 SERVICE WATER SYSTEM (Deleted) t 3/4.7.5 CONTROL ROOM EMERGENCY' AIR CLEANING SYSTEM The operability of the Control Roo.a Emergency Air Cleaning System ensures that occupancy of the Control Room under design basis accident conditions will not result in Control Room personnel receiving radiation exposures in excess of 5 rem.whole body, or its equivalent to any part of the body, for the
'i duration of the accident (GDC 19,10CFR50).
3/4.7.6 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, includfng alpha emitters, is based on 10CFR70.39(c) limits for D
plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of-damage to a source in that group. Those sources which are frequently handled are required to be tested more often'than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed. sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
L YANKEE-ROWE B 3/4 7-4 Amendment No. 52, 83,125 t
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