ML20064A730
| ML20064A730 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/17/1990 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20064A728 | List: |
| References | |
| NUDOCS 9009280004 | |
| Download: ML20064A730 (5) | |
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i 90b9280004 "00917 ADOCK0500g5 PDR-P-
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,; 7 13 0 ? SURVEILLANCE-KCCUIREMENTS 3
Js p&iliaryFeedwaterSystem(Continued) i I'
L BAlii The valve position verifications performed monthly. and following auxiliary
.feedwater system maintenance will confirm the availability of an auxiliary feedwater flow-path to the steam generators.
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The-testing of the auxiliary feedwater pumps every month and:after: cold-shutdowns will verify _their operability by recirculating water to the.
emergency feedwater storage tank..
Operating the regulating valves (HCV-1107A, HCV-11078, HCV-1108A and l-HCV-11088);one at a time every three months and after cold shutdowns will confirm a flow path-to the steam generators and operability of the valves.
Proper functioning of the steam turbine admission valve' and starting of-the feedwater pump will demonstrate the. integrity of the steam. driven-g i pump.. Verification of correct operation will be made both from
~1nstrumentation within the main control room and-direct visual observation n
of the pumps..
The o'perability of the auxiliary feedwater system ensures that the j
- reactor coolant system can be cooled down to less than 300'F from~ normal-i operating conditions at which time the shutdown cooling system may be 1
placed.into operation _in _the event of a total loss of off-site-power.
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j References 4
(1) JSAR, Section 9.4
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(2) tTechnical Specification:2.5 i
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., w 3-62a Amendment No. #,#,#
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w 5.0 ADtilN1STRATIVE CONTROLS or 5.4 Trainina.
- 5. 4.1 = - A retraining and replacement-training program for the plant staff shall be maintained under the direction of the Manager :- Training and shall meet or exceed the requirements-of Section 5.5 of ANSI:
N18.1-1971 and 10 CFR Part 55.
5.4.2 A training program for the firt brigade shall be maintained under the Manager - Training and shall meet or exceed the requirements of-
-Section-27 of NFPA Code-1975, except-that the meeting frequently may be quarterly. :
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,5l5 Review and Audit o
5.5.1 Plant Review Comittee (PRC)
~ Function 5.5.1.l' The Plant Reviet domittee shall function to advi:e the Manager -
Fort Calhoun Station on' all matters related to nuclear. safety.
Comoosition 5.5.1.2 The official: Plc.nt Review Comittee shall be composed of the:
Chairman: Manager'- Fort Calhoun Station Member:
Supervisor - Operations Member:
Manager - Training y
Member:
Supervisor - Maintenance Member:
' Supervisor -_ System Engineering Member:
Reactor Engineer l
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Supervisor - Radiation Protection
. Member:
. Supervisor - Chemistry
-Member:
Assistant Plant Manager l
. Alternates 5.5.1.3 Alternate, members shall be appointed -in writing by. the' Plant Review--
Comittee Chairman to serve on a1 temporary basis; however, no more
- than two alternates shall participate in Plant Review Comittee activities at any one time.
Meetina Freauenqr 5.5.1.4 The Plant Review Comittee shall meet at least once per cakndar month and as convened by the Plant Review Committee Chairman.
Ouorum-5.5.1.5 A quorum of the Plant Review Comittee shall consist of the Chairman and four members including alternates.
5-3 Amendment No. ),JS,JE,Ef,JJJ H
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Discussion:
-This request for Amendment of the Technical Specifications addresses several administrative. changes found on pages 5-3 and 3-62a.
4-Paae-5-5 In order to maintain independence 'between the Plant Review Committee and'its n
'tuditing entities the Manager - Safety Review Group and Manager - Quality.
Assurarce and Quality Control are being deleted and the Assistant Plant Manager and the Reactor _ Engineer are being.added to maintain breath and depth of technical. knowledge.
Paae 3-62a A-reference to FSAR Section 9.4 is corrected to read USAR Section 9.4.
Justification:
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The Co:amission has provided guidance concerning the application of the standards for determining-whether a significant hazards consideration exists by:
y providing certain examples (48 FR 14870) of-amendments that are considered not 1
4 likely.to involve significant hazards consideration.
Example (i) allows for purely administrative change to the Technical Specifications.
The proposed j
changes relate to Example (i) and are purely administrative changes.
Basis for No Significant.'lazards Consideration:
m This proposed change does not involve-significant hazards consideration because operation of-Fort Calhoun Station in accordance with this change would not:
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1.
Involve a-significant increase in the' probability or consequence of an.
accident previously evaluated. This change is administrative.only.-
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This change should change committee' membership and corrects a reference only and would not effect previously evaluated accidents.
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Create the' possibility of a.new or different kind of accident fram-any previously evaluated. This change contains only administrative changes. No new or different modes of operation are proposed for:the pl ant, 3(
Involve a significant reduction in the margin of safety. This change.
- contains only administrative changes and, as such, does not result 'in.
a' decrease in the margin of safety.
Therefore, based on the above considerations, Omaha Public Power District has determined that 'this change does not involve a significant hazards-consideration.
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