ML20051T588
| ML20051T588 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 04/19/1982 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML20051T568 | List: |
| References | |
| 20610, NUDOCS 8205180051 | |
| Download: ML20051T588 (8) | |
Text
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BABOXX 8 WILCDX C0fAlY, COMERCIAL,'lUCLEAR REL PL/ilT USi4RC LICEt1SE Stitt-ll60 IJOCKET 70-1201 SECTIOJ III flVCLEAR SAFETY AtlALYSIS 7.1 General Requirements 7.1.4 Continued modifications to product specifications or design when re-lating to nuclear safety must be reviewed and approved by the Manager, fiaterials Management or his qualified designee and the Safety Board prior to initiation.
In those cases where proposed modifications may involve a change in the basis on which nuclear criticality safety was originally assessed, a technical evaluation by the nuclear criticality safety function will be initiated by the Manager, flaterials Manage-l ment or his qualified designee.
The nuclear criticality safety function noted above is a separate component within the corporate structure and thus is organizationally independent of the CflFP, with no interest in plant operations, other than the nuclear criticality safety aspects.
By established procedure, analyses perfonned by the nuclear criticality safety function involving potential changes in the basis upon which plant safety was orginally assessed are reviewed for appropriateness of method, validity of assumption, and accuracy of the results prior to application in the plant by a qualified individual not involved in the ori-ginal evaluation. Qualifications of the evaluator and re-viewers are given in Section V.
820 518 0 M I DATE 4-19-82 REVISIQ1t;0.
2 PACE 5
CURREi(T REVISIQJ:
SUPERSEDES: PAGE 5
USNRC APPROVAL REFEFS CE DATE l-9 ggygg gg; 1
BMQXX & WIL(DX 01PA#, C0ffERCIAL.1UCLEAR REL PLAIT USNRC LICENSE Snit-ll68 DOCKET M.1201 SECTIO 4 IV HEALTH PHYSICS 17.'
Continued posting plant entrances with signs incorporating the radiation symbol and the following warning:
CAUTI0fl RADI0 ACTIVE l%TERIALS ANY AREA OR C0flTAlilER llITHIll THIS PLANT f4AY C0flTAlti RADI0 ACTIVE IMTERIAL.
This system has been applied effectively at the CNFP for the past ten years.
17.1 Personnel access to the plant and supporting buildings is con-trolled through a guard station which is constantly manned. The plant area is surrounded by a chainlink fence, and all access points, other than the main gate, are locked whe:i not in use.
Key control is the responsibility of Facilities Control.
For purposes of plant and personnel protection and access control, the CNFP " restricted area" is considered to consist of all areas within the perineter fence.
In specific,i.nstances, CNFP manage-ment may modify the restricted area as defined above in order to accommodate unusual or temporary conditions.
17.2 "Cantrolled areas" within the CflFP are established as neces-sary to assist in the protection of personnel or in the control of contamination spread.
Criteria specified in 10 CFR 20.202 and 20.203 are applied to the determination for the necessity of establishing controlled areas.
T 40 DATE 4-19-82 REVISICN NO.
2 PAGE CURREffT REVISION:
SUPERSEmS: PAGE 40 USNRC APPROVAL REFEREitCE 1
DATE 1-9-80 pgg3;g;
PAC 00( & WILOX CDPM/, CORERCIAL,'lUClfAR REL PIM USi1RC LICENSE SNti-llb8 DOCKET 70- 2 1 SECT!04 V C0flDITI0flS 5.0 Administrative 5,4 Independent Auditors are responsible to ascertain the overall performance of the plant functions in providing adequate controls, surveillance, and followup to assure safety and license compliance. This will be accomplished by periodic inspection of the facilities and records resulting in a written report to the Plant Manager.
5,4,1 Qualifications of the independent audi. tors will include competence in the areas of health physics and nuclear physics at least equivalent to those in the Safety functions at CNFP, The independent auditors will have no direct.responsi-bilities for the functions being reviewed, 5,4.2 Designation of the independent auditors will be the responsibility of the Commercial Nuclear Fuel Plant
- Manager, DATE 4-19 82 REVISICr4 NO.
1 PAGE 9
CURRE'fT REVISIG1:
SUPERSEDES: PAGE 9
USNRC APPROVAL RE.rREi1CE t
DATE 4/30/75 REVISICil
BABC00( & WIL(DX C&PM(, CORERCIAL 10 CLEAR REL PIM USNRC LICENSE Snit-ll68 DOCKET 70.1201 V CONDITIONS SECTIO 4 6.0 General Specifications 6.1 Control Program (continued) parameters are reviewed by either the Health-Safety Supervisor or the Manager, Facilities Control who may order the operation suspended if timely compliance cannot be assured.
Disciplinary action can be recommended if warranted.
SAFETY REVIEW BOARD A Safety Revicw Board shall be established to consider the effect of new or revised facilities, to analyze equipment and processes involving radioactive materials and to evaluate the continuing effectiveness of established controls and safeguards, including maintenance of "as 'los as practicable" criteria.
In the case of minor procedural changes and where existing safety practice remains unchanged, the Safety Review Board Chairman or quali fied designee may determine that Board revieIf is not necessary. The ***
Board shall be chaired by the Manager, Materials Management, and the permanent membership shall i
consist of representatives of CNFP operational and technical management. Technical representatives of consulting organi-zation shall be included as necessary (LRC, Nuclear Criticality Safety Group). The Safety Review Board Chairman or his qualified de ***
signee reviews all requests for changes in process and equipment which invo!"e radioactive material and determines if Board i
2 PAGE 13 DATE REVISION NO.
CURRENT REVISIO4:
SUPERSEDES: PAGE 13 USNRC APPROVAL REFEREi1CE I~9-0U I
DATE REVIS M
FABC0C< & WIL(DX COMW, CONEPflAL 'lUClFM REL PLAff USNRC LICENSE SNtt-1163 DOCKET 70-1201 V CONDITIONS SE N 6.d General Specifications 6.1 SAFETY REVIEW BOARD (continued) review is necessary. The Board will not approve any new or revised facility, equipment, or process until it has received written determination (from the Safety Review Board Chairman) for the necessity of a nuclear safety evaluation and/or license amendment, and has reviewed where required, a properly documented nuclear safety evalua-tion or approved license amendment. Board meetings may be convened at the discretion of the Safety Review Board Chairman or the ***
Manager, Facilities Control, but shall be held at least quarterly.
Records of Safety Review Board proceedings, including support-ing calculations and approvafs, will be retained for at least six months after the completion or termination of the subject activity.
RECORDS Operating logs and records of reviews, tests, inspections, personnel qualifications, and, audits shall be maintained on file for review by B&W management and regulatory agencies.
Duration of reccrd retention is based on existing federal regulations, license specifications, custener requirements, and prudent management practices.
2 DATE 4-19-82 REVISIQ1 NO.
PAGE CURRENT REVISICN:
SUPERSEDES: PAGE
'a USNRC APPROVAL REFERENCE 1~9-00 I
DATE REVISICU
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__a BfBCOG( & WILCDX C&PMlY, CGTERCIAL.'lUCLEAR REL PLAlT USNRC L! CENSE SNTt-ll68 DOCx.c 70-1201 SECTICN V CONDITION 7,b Nuclear Safety
~ Technical' Specifications 7.1 General Requirements (continued) 7.1.4.3 Continued g,
for at least 6 months following tennination of the operation.
7.1,4,4 Nuclear safety evaluation is not required where the anticipated change does not affect existing nuclear safety controls or bases. The flanager, Materials Management or his qualified designee determines when a change in product, process, or I
equipment requires a nuclear criticality evaluation or license amendment, 1
1 DATE 4-19-82 REVISIO4 NO.
2 PAGE 36 i
CURRENT REVISIO4:
SUPERSEDES: PAGE 36 UStJRC APPROVAL REFERE!!CE 1
DATE l-9-80 pgygg gg; l
...3 BABCDC< & WILQR COM#, ONEPflAL,'luCLEAR REL PIM USNRC LICENSE Stitt-ll68 DOCKET 70-1201 V C0flDITI0flS SECTIO 4 8.b Technical Specifications - Radiation Safety 8.1 Effluents to Unrestricted Areas 8.1.1 Continued c.
The following program shall be instituted to assure that airborne releases to uncontrolled areas are main-tained as low as practicable:
Quarterly Average - % of 10 CFR 20 Appendix 3, Table 2 LIMIT ACTI0fl 1 10% of "itPC" None required.
11 - 20%
Conduct investigation of system and correct if possible.*
21 - 75%
Visually inspect system. As soon as practicable, conduct efficiency test. Determine and correct cause.**
> 75%
Conduct immediate investigation to determine and correct problem in ventilation system. Maintain addi-tional Health-Safety surveillance of system to monitor contamination levels until problem is corrected.
- end weld cperation area - none required
d.
Pre-filters serving equipment in the pelletizing area will be instrumented and monitored as speci-fied in 8.1.la above.
8.1.2 Potentially contaminated liquid effluents will be controlled through a retention tank system with dilution and mixing capabilities and shall be evaluated DATE 4-19-82 REVISICH NO.
3 PAGE 76 CURRENT REVISION:
SUPERSEDES: PAGE 76 USNRC APPROVAL REFERENCE DATE 6-12-80 REVISIci 2
E4 COG ( & WILCDX C&PA#, CafEPflAL.1UClfAR REL PlM USNRC LICENSE Stift-llb8 DOCKET E.1201 SECTIO 4 V CONDITI0 tis 8.0 Technical Specifications - Radiation Safety 8.1 Effluents to Unrestricted Areas 8.1.2 Continued for compliance with 10 CFR 20, Appendix B limits prior to release to unrestricted areas. The following actions, at the contamination levels indicated, will be undertaken in order to maintain contaminated liquid effluent re-leases as low as practicable:
% 10 CFR 20 App. B. "f1PC" Action
< 20%
No action required.
21-75%
Individual releases authorized by Plant Manager or his alter-nate.
> 75%
Discharge prohibited. Waste routed for further treatment or disposal by burial.
Facilities Control shall maintain records of investigations and actions resulting therefrom, a.
Retention tanks will be inspected monthly for sludge accumulation.
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I 77 DATE 4-19-82 REVISIQ1 NO. 2 PAGE CURRENT REVISION:
SUPERSEDES: PAGE 77 USNRC APPRCML EFERENCE DATE l-9-80 ggyg3gg; 1
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