ML20052F828
| ML20052F828 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/06/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F829 | List: |
| References | |
| NUDOCS 8205140012 | |
| Download: ML20052F828 (8) | |
Text
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4, UNITED STATES
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g NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 16, 1982 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 application, the provisions of the Act, and the. rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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.T 8205140012 820506 PDR ADOCK 05000338 PDR P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License i
No. NPF.4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ob Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Techical Specifications i
Date of Issuance: May 6, 1982 I
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PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
The representative sa=ple selected for functional testing shall -
include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sa=ple shall include snubbers from the following e
three categories:
1.
The first snubber away from each reactor vess'el nozzle 2.
Snubbers within 5 feet of heavy equip =ent (valve, pump, turbine, =otor, etc.).f 3.
Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Re=ove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sa=ple.*
Tables 3.7-4a and 3.7-4b =ay be used jointly or separately as the basis for the sa=pling plan.
In addition to the regular sa=ple, snubbers which failed the previous' functional test shall be retested during the'next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another pesirion) and the spare snubber shall be retested. Test results of these snubbers =ay not be included for the re-sa=pling.
If any snubber selected for functional testing either fails to lockup or fails to =ove, i.e., frozen in place, the cause vill be evaluated and if caused by =anufacturer or design deficiency all snubbers of the sa=e design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the require =ents sected above for snubbers not meeting the functional test acceptance criteria.
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- #The require =ent to functionally test large snubbers greater than 50,000 kips l around the stea= generators and reactor cool' nt' pu=ps, is' exe=pt fro:
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functional testing for the representative sa ple of snubbers selected for i
l testing during the cycle 3 refueling and =aintenance outage.
- Per=anent or other exe=ptions from functional testing for individual snubbers in these categories =ay be granted by the Co==ission only if a justifiable
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basis for exe=ption is presented and/or snubber life destructive. testing was perfor=ed to qualify snubber operability for all design conditions at either the ce=pletien of their fabrication or at a subsequent date.
NCRTE ANNA - UNIT 1 3/4 7-29:
Amendment No. 27, 40 l
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PLANT SYSTEMS SURVEILLANCE REQUIR { TS (Continued)
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this enginerring evaluatica shall be to. determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in e
order to ensure that the supported component remains capable of meeting the design service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic sniaber functional test shall verify that:
1.
Activation (restraining action) is achieved.vithin the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release race, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand lead without displacement shall be verified.
- e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
- 1. The force that initiates free movement of the snubber rod in either cension or compression is less chan the specified =ax1=um drag force.
Drag force shall not have t'ncreased more chan 50% since the last functional test.
- 2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and co=pression.
- 3. Snubbei release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load
. ithout displacement shall be verified.
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- f. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life com=ences and the installation and maintenance records on which the designated service life is based shall be =aintained as required by Specification 6.10.2.
NcRTH ANNA - UNI *. 1 3/4 7-19b Amendment NO. 32, 40
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PLANT SYSTEMS SURVEILLANCE REAUIREMENTS (Continued)
At least once per 18 uenths, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated' service life will be exceeded prior to the next scheduled snubber service life review,'the snubber service life shall be reevaluated or the snubbe,r shall be replaced or recondi,tioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
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_y NORTF. ANNA - UNIT 1 3/4 7-29c Amendment No. 40 e
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k8 HGO UNITED STATES s.,f [k NUCLEAR REGULATORY COMMISSION
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WASHINGTON,0. C. 20555 Q v4 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 16, 1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Commission; C.
There is reasonable 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 Comission'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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements
.i -
have been satisfied.
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r 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Tehenical Specification The Technical Specifications contained in Appendiges A and B, as revised through Amendment No. 24 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION R i A GEh~
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1982
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h
PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
The representative sample selected for functional testing shall include the various configurations, operating environ =ents and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sa=ple shall include snubbers fro =.the folleving three categories:
1.
The first snubber away fro = each reastor vessel noz:le 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine. =otor', etc. ).#
,a 3.
Snubbers within 10 feet of the discharge fro = a safety relief valve.
Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Re=ove" or in "High Radiation Zones During Shutdown" shall also be included in the representative saeple.* Tables 3.7-4a and 3.7-4b =ay be used jointly or separately as the basis for the sa=pling plan.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the re-sa=pling.
If any snubber selected for functional testing either fails to lockup or fails to =ove, i.e.,
frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all l
snubbers of the sa=e design subject to the sa=e defect shall be functionally tested. This testing require =ent shall be independent of the require =ents stated above for snubbers not =eeting the functional test acceptance criteria.
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l
T aThe require =ent to functionally test large snubbers greater than 50,000 kips, around the stea= generators and reactor coolant pu=ps, is exe=pt fro = functienal testing for the representative sa=ple of snubbers selected for testing during the Cycle 1 refueling and =aintenance outage.
- P e r=anen t or other exe=ptions fro = functional testing for individual l
l snubbers in these categories =ay be granted by the Co==ission only if a justifiable basis for exe=ption is presented end/or snubber life destructive testing was perfor=ed to qualify snubber operability for all design conditions at either the ce=pletion of their fabrication or at a subsequent date.
NCRTH ANNA - UNIT 2 3/4 7-25b Amendment No. I3, 24 r
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PLANT SYSTEMS SURVEILLA(CE REQUIREMENTS (Continued)
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the sn' bber(s). The purpose u
of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely af fected by the inoperability of the snubber (s) in order to ensure that the supported component remain's capable of meeting the design service.
d.
Hvdraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
'1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and ce=pression.
2.
Snubber bleed, or release rate, where required, is within the specified range in ec=pression or tensi3n. For snubbers specifically required to not displace uader continuous load, the ability of the snubber to withstand load without displace =ent shall be verified.
Mechanical Snubbers Functional Test Accentance Criteria 4
e.
The =echanical snubber functional test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or ce=pression is less than the specified maximum drag force'.
Drag force shall not have increased more than 50% sinc *e the last functional test.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and eccpression.
3.
Snubber release rate, where required, is within the specified range in ce=pression or tension. For snubbers specifically
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-required not to displace urder continuous lead, the ability of the snubber to withstand load withodt displace =ent shall be verified.
f.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life ce==ences and the installation and mainte-nance records on which the designated service life is based shall be
=aintained as required by Specification 6.10.2.
NORTH ANNA - UNIT 2 3/4 7-26c Amendment No. 13, 24
PLANT SYSTEMS SURVEILLANCE R5QUIREMENTS (Continued)
At least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or vill not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service l'1fe shall be' reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the,next scheduled service
, life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
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NCRTH ANNA - UNI; ;
3/4 7-26d Amendment No. 23, 24
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