ML18057B440: Difference between revisions

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Reports shall be prepared and distributed as indicated below: . a. The results of reviews, performed pursuant to Section 6.5.2.4.1 . and Section 6.S.2.4.2, shall be reported to the Vice President  
Reports shall be prepared and distributed as indicated below: . a. The results of reviews, performed pursuant to Section 6.5.2.4.1 . and Section 6.S.2.4.2, shall be reported to the Vice President  
-NOD at least
-NOD at least
* b. A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.  
* b. A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.
 
6.5.3 PLANT SAFETY ANO LICENSING 6.S.3.1. FUNCTION 6.5.3.2 6.5.3.3 The Pl ant Safety and Licensing organization shall funct1.on to examine industry operating experience and proposed changes in design or operation .to identify issues significant to nuclear safety and recornnend nuclear safety improvements.
====6.5.3 PLANT====
SAFETY ANO LICENSING 6.S.3.1. FUNCTION 6.5.3.2 6.5.3.3 The Pl ant Safety and Licensing organization shall funct1.on to examine industry operating experience and proposed changes in design or operation .to identify issues significant to nuclear safety and recornnend nuclear safety improvements.
COMPOSITION  
COMPOSITION  
--The Plant.Safety and Licensing staff shall be composed of at least five experienced technical staff, reporting to.the Plant Safety and Licensing Director, to carry out RESPONSIBILITIES The Plant Safety and licensing staff may .provide nuclear safety review as delegated by PRC.for: a. Procedures, programs and changes thereto identified in Specification 6.8 and any additional  
--The Plant.Safety and Licensing staff shall be composed of at least five experienced technical staff, reporting to.the Plant Safety and Licensing Director, to carry out RESPONSIBILITIES The Plant Safety and licensing staff may .provide nuclear safety review as delegated by PRC.for: a. Procedures, programs and changes thereto identified in Specification 6.8 and any additional  
Line 92: Line 90:
* d. The Site Emergency Plan. 6-9 Amendment No. JJ, JJ, J,J, Jt7   
* d. The Site Emergency Plan. 6-9 Amendment No. JJ, JJ, J,J, Jt7   
** ADM IN I ST RAT I YE INTROL s 6.5.3.4 6.5.3.5 AUTHORITY.
** ADM IN I ST RAT I YE INTROL s 6.5.3.4 6.5.3.5 AUTHORITY.
The Plant Safety and Licensing staff shall determine those issues significant to nuclear safety which require review by the Plant Review Convnittee from items considered under Specification 6.5.3.3.a through d. For those items not referred to PRC, Plant Safety and licensing shall recommend in writing to plant management approval or disapproval of items considered under 6.5.3.3. RECORDS Reports of Plant Safety and licensing activities pursuant to Specification 6.5.3.3 shall be submitted monthly to PRC. 6.6 <Qeletedl  
The Plant Safety and Licensing staff shall determine those issues significant to nuclear safety which require review by the Plant Review Convnittee from items considered under Specification 6.5.3.3.a through d. For those items not referred to PRC, Plant Safety and licensing shall recommend in writing to plant management approval or disapproval of items considered under 6.5.3.3. RECORDS Reports of Plant Safety and licensing activities pursuant to Specification 6.5.3.3 shall be submitted monthly to PRC. 6.6 <Qeletedl 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
 
===6.7 SAFETY===
LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
: a. The shall be shut down inmedhtely and not restart.ad until the Co111111ssion authorizes resumption of operation (10 CFR 50.36(c)(l)(i)(A)).
: a. The shall be shut down inmedhtely and not restart.ad until the Co111111ssion authorizes resumption of operation (10 CFR 50.36(c)(l)(i)(A)).
: b. The safety limit violation shall be reported within 1 hour to the Co11111ission in accordance with 10 CFR 50.36, as well as to the Vice President
: b. The safety limit violation shall be reported within 1 hour to the Co11111ission in accordance with 10 CFR 50.36, as well as to the Vice President
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Nuclear Operations and to the NPAO. 6*10 Amendment No. JJ, JJi, Jtl   
Nuclear Operations and to the NPAO. 6*10 Amendment No. JJ, JJi, Jtl   
* * * . . . . AOMINISTM!IvE CONTROLS 6.9.3.3 6.10 .. 6.10.l Special Reports a. Special Reports shall be submitted to the NRC covering the* activities identified below pursuant to the requirements of the applicable referenced specifications:
* * * . . . . AOMINISTM!IvE CONTROLS 6.9.3.3 6.10 .. 6.10.l Special Reports a. Special Reports shall be submitted to the NRC covering the* activities identified below pursuant to the requirements of the applicable referenced specifications:
* Specification Reporting Area Reference Dye Prestressing, Anchorage, 4.5.4 Liner and Penetration  
* Specification Reporting Area Reference Dye Prestressing, Anchorage, 4.5.4 Liner and Penetration 4.5.5 Tests 90 Days After Completion of the Test* *A test 1s considered to be coinpl ete after all associated mechanical, chemical, etc., tests have been completed.
 
====4.5.5 Tests====
90 Days After Completion of the Test* *A test 1s considered to be coinpl ete after all associated mechanical, chemical, etc., tests have been completed.
: b. Special reports shall be submitted in accordance with lOCFRS0.4, within the time period specified for each report
: b. Special reports shall be submitted in accordance with lOCFRS0.4, within the time period specified for each report
* RECORD RETEN1ION  
* RECORD RETEN1ION  
Line 121: Line 113:
* > *ApMtNISTRATtVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement tra;ning program for the plant staff shall be ma; ntained and sha 11 meet or exceed the requirements and ; recommendations of Section 5.5 of ANSI NlS.1-1971 and Appendix qA" of 10 CFR Part 55.
* > *ApMtNISTRATtVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement tra;ning program for the plant staff shall be ma; ntained and sha 11 meet or exceed the requirements and ; recommendations of Section 5.5 of ANSI NlS.1-1971 and Appendix qA" of 10 CFR Part 55.
* 6.4.2 The Fire Brigade training program shall be maintained and shall, as t practicable, meet or exceed the requirements of Section 27 of the* NFPA Code-1975.
* 6.4.2 The Fire Brigade training program shall be maintained and shall, as t practicable, meet or exceed the requirements of Section 27 of the* NFPA Code-1975.
Fire brigade training drills shall be held at least quarterly.  
Fire brigade training drills shall be held at least quarterly.
 
6.5. REVIEW AND AUQ[J 6.5.1 PLANT REVIEW COtt!ITTEE lPRCl 6.5.1.1 FUNCTION The Plant Review Connittee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety. COMpoStTION The PRC shall be composed of: _ Chairman:
===6.5. REVIEW===
AND AUQ[J 6.5.1 PLANT REVIEW COtt!ITTEE lPRCl 6.5.1.1 FUNCTION The Plant Review Connittee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety. COMpoStTION The PRC shall be composed of: _ Chairman:
Member: Member: . Member: Member: Mefllblr:
Member: Member: . Member: Member: Mefllblr:
Member: Member: Member: Plant General Mana91r Operations Manager
Member: Member: Member: Plant General Mana91r Operations Manager
Line 297: Line 287:
* CONTROLS 6.9.3.3 6.10 6.10.l Special Reports a. Spec h 1 Reports sha 11 be submitted to the NRC cover; ng the
* CONTROLS 6.9.3.3 6.10 6.10.l Special Reports a. Spec h 1 Reports sha 11 be submitted to the NRC cover; ng the
* act1v;t1es identified below pursuant to the requirements of the applicable referenced spaciffcatfons:
* act1v;t1es identified below pursuant to the requirements of the applicable referenced spaciffcatfons:
Specification Reporting Ref1ranc1 OU1 Area Prestressin9, Anchorage, 4.5.4 Liner and Penetration  
Specification Reporting Ref1ranc1 OU1 Area Prestressin9, Anchorage, 4.5.4 Liner and Penetration 4.5.5 Tests 90 Days After Completion of the Test* *A test is considered to be cofl1)1ete after all associated t mechanical, chemical, etc., tests have been completed. . i b. Special reports shall be subllitted in accordance with 10 CFRS0.4, within th* time period specified for each report. _ RECORD BETENJlON . .
 
====4.5.5 Tests====
90 Days After Completion of the Test* *A test is considered to be cofl1)1ete after all associated t mechanical, chemical, etc., tests have been completed. . i b. Special reports shall be subllitted in accordance with 10 CFRS0.4, within th* time period specified for each report. _ RECORD BETENJlON . .
* t_ In addition to th* appl 1cabl.* record retention requirt1111nts of Title { . 10, Code of Federal Regulations, the following records shall be *retained for at least the minilllUll period indicated:
* t_ In addition to th* appl 1cabl.* record retention requirt1111nts of Title { . 10, Code of Federal Regulations, the following records shall be *retained for at least the minilllUll period indicated:
The following records shall.be retained for at least five years: a. Records and logs of fac11tty operatton covering time interval at each pa.er 11v1l. f>. Records and logs of prtnctpal 111intenanc1 act1Y1ttes, inspections, repatr and replacltllftt of principal items* of equiP119nt related to nuclear safety. c. All ,..,ortabl*
The following records shall.be retained for at least five years: a. Records and logs of fac11tty operatton covering time interval at each pa.er 11v1l. f>. Records and logs of prtnctpal 111intenanc1 act1Y1ttes, inspections, repatr and replacltllftt of principal items* of equiP119nt related to nuclear safety. c. All ,..,ortabl*

Revision as of 18:07, 5 May 2019

Proposed Tech Specs 6.5.1.2 Re Composition of Plant Review Committee & 6.5.2.2 Re Reporting Responsibilities of Plant Review Committee
ML18057B440
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/20/1991
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057B439 List:
References
NUDOCS 9201030256
Download: ML18057B440 (30)


Text

( I I ** ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED ORGANIZATIONAL TECHNICAL SPECIFICATION CHANGES -REVISION 1 REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGES 9201030256 911220 PDR ADOCK 05000255 P PDR : __ December 20, 1991 9 Pages *.,

citlf Robs

  • 6.4 TBAINING A retraining and replacement training program for the plant staff shall be maintained and shall meet or exceed the requirements and reconmendations of Section 5.S of ANSI NlS.1-1971 and Appendix "A" of 10 CFR Part 55. . 6.4.2 The Fire Brigade training program shall be maintained and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975.

Fire brigade training drills shall be held at least quarterly.

6. 5 REV I'EW AND AUD IT 6.5.1 PLANT REVIEW COMMITTEE CPRC) 6.5.1.1 FUNCTION The Plant Review Co11111ittee

{PRC) shall function to advise the Plant *General Manager on all matters related to nuclear safety. --6. 5. 1. 2 COMPQS IT ION --. _,.,.--*-.. . . . The PRC is composed of. ni11e regular members from either the Palisades staff or the Nuclear Erig(neering and Construction Organtzatton

{NECO) staff. The qualification level for PRC members shall be at least equivalent to those described in of ANSI NlS.1-1971.

The / PRC shall include representatives from the Operations, Radiological . Services, Maintenance and Engineering Departments.

The members shall be designated in administrative procedures by the Plant General Manager. The Plant General Manager shall also designate

_the Chairman and Alternate Chairmen in writing. 6.5.1.3 ALTERNATES Alternate members of."the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. No more than*two alternates shall participate as voting members at any one time tn PRC act1v1ttes.

6-S Amendment No.

  • ADMINISTRATIVE CONTROLS **s.s-.1.4 MEETING FREQUENCY The PRC shall meet at least once per calendar month with special meetings as required.
6. 5. 1. 5 QUORUM A quorum of the PRC shall consist of the Chairman or Alternate I / Chairman and four members (including 6.5.1.6 RESPONSIBILITIES The PRC shall be responsible for nuclear safety review of: a. All procedures and programs specified by Specification 6.8 and changes thereto, and any other procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety; all proposed tests or experiments that affect nuclear safety; all proposed changes or modifications to plant systems or equipment that affect nuclear safety; and the Site Emergency Plan.
  • _ -b. All proposed changes to Operating License and Technical Specifications.
c. Results of investigations of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations "to prevent recurrence and be forwarded to the Vice President
  • NOD and to the Director, Nuclear Performance Assessment Department (NPAD).) d. Plant operations to detect potential safety hazards. e.
  • Reports of special reviews and investigations as requested by the Plant General Manager or NPAD. f. All reportable events as defined in Sectton 6.9.2. g. All items under Specification 6.5.3.4 as significant to nuclear $afety.
  • h. Monthly reports from Plant Safety and l_icensing
  • . PRC review of the above items may be performed by routing, subject to the requirements of Specification 6.5.1.7. PRC may delegate review of item a. to Plant Safety and Licensing as described 1n Specification 6.5.3 6-5a Amendment No.

Jil :

  • ADMINISTRATIVE CONTROLS -6. 5 .1. 7 -AUTHOB*rTy The PRC shall: a.
  • Recommend in wr;ting to the Plant General Manager approval or disapproval of items considered under Specifications 6.5.1.6.a.

through h. above. b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.S.l.6:a, b, c and g above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President

-Nuclear Operations and to the Nuclear Performance Assessment Department of any disagreements between the PRC and the Plant General Manager; however, the Plant General Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above. . . The PRC Chairman may recommend to the Plant General Manager approval of those itemsJdentified in Specification above based routing review provided the following conditions are met: (1) at -least five PRC members including the Chairman and no more than 2*' alternates, shall review the item, concur with determination as to whether or not the item const;tutes an unreviewed safety question, and provide written convnents on the item; (2) all comments *$hall be. resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.

The item shall be reviewed at a PRC meeting in the event that: . (l) Comments are not resolved; or (2) the Plant General Manager overrides the reco11111endations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or. (4) the item was reportable to the NRC. 6.S.1.8 RECORDS The PRC shall maintain minutes of each PRC meeting and shall provide copies. to the NPAD. *. t 6-6 Amendment No. lJ, JJ, JJ, Jil ADMINISTBATIVE CONTROLS 6.5.2 -NUCLEAR PERFORMANCE ASSESSMENT DEPARTMENT (NPADl 6.5.2.1 FUNCTION The Nuclear Performance Assessment Department (NPAD) shall function to provide independent review of activities in the areas of: a. Nuclear power plant operation

b. Nuclear engineering
c. Chemistry and radiochemistry
d. Metallurgy
e. Non destructive testing f. Instrumentation and control g. Radiological safety h. Mechanical and electrical engineering
i. Administrative controls and quality assurance practices
j. Emergency planning k. Training 6.5.2.2 COMPOSITION

-.

  • The NPAD shall jflclude the Director, who reports to the Vice President

-NOD, and a full-time staff of Nuclear Performance Specialists reporting to the Director.

The Director.

and the Nuclear Performance Specialists shall meet or exceed the qualifications described in Section 4.7 of ANSI/ANS 3.1-1987.

The NPAD shall have no direct responsibility for acthities subject to its review. 6.5.2.3 CONSULTANTS If sufficient expertise is not available within NPAD to review particular issues, the NPAD shall have the authority to utilize consultants or other qualified organizations for expert advice. 6.5.2.4 RESPONSIBILITIES 6.5.2.4.1 REVIEW The NPAD shall review: a.-,The safety evaluations for: 1) changes to procedures, equipment or systems, and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59. 6-6a Amendment No. 7J, JJ, J-,

Jtl I I e ADMINISTRATIVE CONTBQLS 6.5.Z.4.l REVIEW (Continued)

c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59. d. Proposed changes to Technical Specifications or the Operating License. e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f. Significant operating abnonnal1t1es or deviations from normal and expected perfonnance of unit equipment that affects nuclear *safety. g. All reportable events having nuclear safety significance.
h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety. t. Reports meeting minutes of the Plant Review Co111nittee.

6.5.2.4.Z.

AUDITS Audits of safety-related facility activities shall be perfonned by.the NPAD staff under the cognizance of the* Nuclear Performance Specialists.

These audits shall encompass:

a. The conformance of plant operation to provisions contained within the Technical Specifications and applicable license, conditions at least once per 12 months. b. The performance, training and qualifications of the entire facility staff at least once per 12 months. c. The performance of activities required by the Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A) to meet the critert* of 10 CFR 50, Appendix B at least once per 24 months. * ' d. The Site Emergency Plan and implementing procedures at least once per 12 months. e. The Stte Security Plan and implementing procedures (as required by the Stte Security Plan) at least Qnce per 12 months. 6-7 Amendment No. JJ,
  • ** ADHINISTBATIYE CONTROLS 6.5.2.4.2 AUPITS (Continued)
f. Any other area of plant operation considered appropriate by NPAD or the Vice President

-Nuclear Operations.

g. The plant Fire Protection Program and implementing procedures at least once per 24 months. h. An independent fire protection and loss prevention inspection and audit to be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm. 1.. An inspection and audit of the fi.re protection and loss prevention program to be performed by an outside qualified fire consultant at intervals no greater than 3 years. j. Radiological environmental monitoring program and the results thereof at least once per 12 months. k. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. 1. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. Audit reports encompassed by Specification 6.5.2.4.2 above shall be forwarded to the Director NPAD, and Management positions , responsible for the areas audited within thirty (30) days after completion of the audit. 6.5.2.4.3 NPAD review of the subjects in Specifications 6.5.2.4.1 and 6.5.2.4.2 shall be performed by an assigned Nuclear Performance Specialist
  • selected on the basis of his technical

'expertise relative to the subject being reviewed.

If the assigned Nuclear Performance Specialist determines the need for interdisciplinary review, a connittee consisting of the Director, NPAD, or his designate, and at least four Nuclear Performance Specialists, shall be assigned.

Such comittee shall meet as conditions requiring..

  • -( 6.5.2.5 review arise, but no less than twice yearly AUTHORIU The NPAD shall report to and advise the Vice President

-NOD of . significant findings associated with those areas of responsib11 ity specified in Sections 6.5.2.4.1 and Section 6.5.2.4.2.

6-8 Amendment No. JJ, JJ, Jt7 ADMINISTBATIVE

  • 6.5.2.6 Records of NPAO activities shall be maintained.

Reports shall be prepared and distributed as indicated below: . a. The results of reviews, performed pursuant to Section 6.5.2.4.1 . and Section 6.S.2.4.2, shall be reported to the Vice President

-NOD at least

  • b. A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.

6.5.3 PLANT SAFETY ANO LICENSING 6.S.3.1. FUNCTION 6.5.3.2 6.5.3.3 The Pl ant Safety and Licensing organization shall funct1.on to examine industry operating experience and proposed changes in design or operation .to identify issues significant to nuclear safety and recornnend nuclear safety improvements.

COMPOSITION

--The Plant.Safety and Licensing staff shall be composed of at least five experienced technical staff, reporting to.the Plant Safety and Licensing Director, to carry out RESPONSIBILITIES The Plant Safety and licensing staff may .provide nuclear safety review as delegated by PRC.for: a. Procedures, programs and changes thereto identified in Specification 6.8 and any additional

  • procedures and changes thereto identified by the Plant General Manager as significant to nuclear safety. b. proposed tests or experiments.

c *. All proposed changes or modifications to plant systems or -: equipment.

    • ADM IN I ST RAT I YE INTROL s 6.5.3.4 6.5.3.5 AUTHORITY.

The Plant Safety and Licensing staff shall determine those issues significant to nuclear safety which require review by the Plant Review Convnittee from items considered under Specification 6.5.3.3.a through d. For those items not referred to PRC, Plant Safety and licensing shall recommend in writing to plant management approval or disapproval of items considered under 6.5.3.3. RECORDS Reports of Plant Safety and licensing activities pursuant to Specification 6.5.3.3 shall be submitted monthly to PRC. 6.6 <Qeletedl 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a. The shall be shut down inmedhtely and not restart.ad until the Co111111ssion authorizes resumption of operation (10 CFR 50.36(c)(l)(i)(A)).
b. The safety limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Co11111ission in accordance with 10 CFR 50.36, as well as to the Vice President
  • Nuclear Operations and to the NPAD. c. A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification. (The safety limit violation and the report shall be reviewed by the PRC.) d. The report .. shall be submitted within 14 days to the Conmission (in accordance with the requirements of 10 CFR 50.36), to the Vice President"**

Nuclear Operations and to the NPAO. 6*10 Amendment No. JJ, JJi, Jtl

  • * * . . . . AOMINISTM!IvE CONTROLS 6.9.3.3 6.10 .. 6.10.l Special Reports a. Special Reports shall be submitted to the NRC covering the* activities identified below pursuant to the requirements of the applicable referenced specifications:
  • Specification Reporting Area Reference Dye Prestressing, Anchorage, 4.5.4 Liner and Penetration 4.5.5 Tests 90 Days After Completion of the Test* *A test 1s considered to be coinpl ete after all associated mechanical, chemical, etc., tests have been completed.
b. Special reports shall be submitted in accordance with lOCFRS0.4, within the time period specified for each report
  • RECORD RETEN1ION

.... . In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated( The following records.shall be retained for at 1 east five years: a. Records and logs of facility operation covering.time interval at each power level. . b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety. ** c. *All reportable events as defined tn Section 6.9.2. d. Records of surveillance activities, inspections and caltbrat1ons required by these Technical Speciftcattons.

! . 6-26 Amendment No. tJ, JJ, ..

  • ATIACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED ORGANIZATIONAL TECHNICAL SPECIFICATION CHANGES -REVISION 1 EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED UP EXISTING TECHNICAL SPECIFICATIONS PAGES December 20, 1991 10 Pages
  • INSERTS (A} "6.5.1.2 COMPOSITION The PRC is composed of nine regular members from either the Palisades staff or the Nuclear Engineering and Construction Organization (NECO) staff. The qualification level for PRC members shall be at least equivalent to those described in Section 4.4 of ANSI NlS.1-1971.

The PRC shall include representatives from the Operations, Radiological Services, Maintenance and Engineering Departments.

The members shall be designated in administrative procedures by the Plant General Manager. The Plant General Manager shall also designate the Chairman and Alternate Chairmen in writ i r,g. * (B) *6.5.2.2 COMPOSITION The NPAD shall include the Director, who reports to the Vice President

-NOD, and a full-time staff of Nuclear Performance Specialists reporting to the Director.

The Director and the Nuclear Performance Specialists shall meet or exceed the qualifications described in Section 4.7 of ANSI/ANS 3.1-1987.

The NPAD shall have no direct responsibility for activities subjecl. to its review.* (C) Audits of operational nuclear safety-related facility activities shall be performed by the NPAD staff under the cognizance of the Nuclear Performance Specialists.

These audits shall encompass: (D) NPAD review of the subjects in Specifications 6.5.2.4.1 and 6.5.2.4.2 shall be performed by an assigned Nuclear Performance Specialist selected on the basis of technical expertise relative to the subject being , reviewed.

If the assigned Nuclear Performance Specialist determines the need for interdisciplinary review, a coJTmittee consisting of the Director, NPAD, or his designate, and at least four Nuclear Performance Specialists, shall be ass.igned.

Such coJTmittee shall meet as conditions requiring interdisciplinary review arise, but no less than twice yearly.

  • > *ApMtNISTRATtVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement tra;ning program for the plant staff shall be ma; ntained and sha 11 meet or exceed the requirements and ; recommendations of Section 5.5 of ANSI NlS.1-1971 and Appendix qA" of 10 CFR Part 55.
  • 6.4.2 The Fire Brigade training program shall be maintained and shall, as t practicable, meet or exceed the requirements of Section 27 of the* NFPA Code-1975.

Fire brigade training drills shall be held at least quarterly.

6.5. REVIEW AND AUQ[J 6.5.1 PLANT REVIEW COtt!ITTEE lPRCl 6.5.1.1 FUNCTION The Plant Review Connittee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety. COMpoStTION The PRC shall be composed of: _ Chairman:

Member: Member: . Member: Member: Mefllblr:

Member: Member: Member: Plant General Mana91r Operations Manager

  • Engineering and Maintenance Mtnager Radiological Services Manager
  • Plant Safety and Licensing Director .Reactor Eng1neer1ng Superintendent Op1rat1on1 Superintendent Instru111ntat1on and Control Superintendent Shift Supervisor or Shift Eng1n .. r(s) (1) *may s1rv1 11 Des1gnattd Alternate for the Chat,..,.

6.5.1.3 ALTEBNATES Alternate 11ibers of the PRC shall be appointed tn wr1t1ng by th* PRC Chatrman to serve on a t911Porary basts. No llOrt than two alternates shall parttctpat1 as voting lllltlbers at any one t.1* in PRC . *act1v1t111.

M1*1r1 wt\8' a 19*1ri1kS 1

  • J ft11te*4e1t

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        • 111 fer v1*tR9 pUSJOStl 6*5 Amendment No.

May i11 1991

.* ..,., .*

  • . !' YY'IW'IJ't1=*
  • *-.... ' . -.. -... -. . . . .. -) 5.,,l,4 R!SPONStlttITtlS The PIC *hall be r1.,oa1tble for iiultar 1af1cy rnitv of: ** All proct4urt*

uul pro1r ... 1,ectfie4 b1 Spectficacioa 6.9 aDd cb ..... cbereco, alMI &af ocller proce4Qrt*

or cbanc** cb1r1co aa d*C*nd***

bJ clle Pl&ac C.aeral Kaaac*r co atf ecc auclear 1afecy1 all pro,o1 .. c1aca or ea,ertaeac1 chac alf1cc.aucl1ar M11c,1 all pn,o ... chac** or mo41f1cactotaa co pt.Ac .,,, ... or tqQt,...c cbac atf1c1 iiul1u 1af1c11 IM. ell* sue !Mqncy ftaa. . b. ill pn,o ... chat** co 0,.ractq tlc1Ue ... 'fec!mical Speciftcactou.

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) -* ADMINISTUTIVE 11,..._----------.

-#SS';s.f (N.PA D) 6.S.2 NUCLEAI BM'BW fJBftVIGIG DEPARTMENT

{llHC) 6.S.2.1 . lOlfCTlOB

/IVPAD) I l / The Nuclear h 11 Department shall function to provida independent reviev of activities in the area* of: f:,: 6.S.2.2 6.S.2.l a. Nuclear power plant operation

b. Nuclear en9ineerin1
c. Chemistry and radiochem18try
d. Metallurgy
e. Nonde*tructive testin1 f. Instrumentation and control g. Radiological safety
  • h. Mechanical and electrical engineerin1
i. Adainistrative controls and quality a**Ul'ance practice*
j. Emergency Planniq k. Training COOOSITIOB The NSSD shall conai*t of a full-tm staff appoilltecl by au _reportin1 to the Vice Pre*ideat

-NOD* NSSD staff-*hall have no direct r1spon*ibility for'activitiea subject to their

  • review. The NSSD staff shall meet or exceed the qualif icatiou de*cribed ill Section 4.7 of ANSI/ANS 3.1 -1987. CONST1LTAHTS . .

l'r'MD . . If sufficient apertiH

  • not-available vithill fi689. to review particular iseuea, the .__.*hall have the authority to utilize conaultata or other qualified orgataatiou for expert advice. 6.S.2.4 -R!SPOSSIIILITIIS 6.S.2.4.1 llEVt!V /YP.4D '11le._.,.

pan rmns .-: The uf*t.y naluatiou forz . O chan1** to procedure*, . _;:

  • equipae or ayat ... , and . 2) teat* or completed th** prorisiona of 10 en so.st to verify t-t such * * ** action* do not c0111titute an unreviend safety que*tioa.
b. Propo*ad chaa** to procedur***

equipunt or syat ... -vhich involv* Ul unrmevecl safety qu**tion ** defined ill 10 era 50.59. TSP0189-0001-NL04

.*. I 6-6*

  • Aaenctm.Dt No. ti, 7J, IJ, Jf, te*, ........ 16, 1918. I I I I I I I I t. I
  • -*) **w*'l,'*:4,A.*""":'
  • -\-'"JI"'**
  • -. . . . . . . . . . . . . ......

6.5.Z.4.2

' . * *

  • trt:r. (Coftcinuad)
c. Propo1ed ce1c1 or expert:enc1 involve an 1.1nr1vtavecl utacy q1.111cioa H dafinect 11'1 LO GF'll 50. 59. d. Propo1ect chais1** co Technical Speciticaciofta or ch* Operac1a1 LLc1n1e. ** 1iolac101ta of cod1a, r1aulac101ta, order1, Technical Spec1f1cacton*, Licea** r1quir1 .. ac1, or of 1nc1ra&l procedure*

or icacr'\lcct01ta haV1.c1 aucl1ar 1af 1cy 1tp1f tcaac1. . t. Sip1f1caat o'eractnc abao'9.Altct1*

or d..-tacton*

troa aoraal &!Ml ezpeccecl perf oraaAca of 'ltiit chac alf1cc1 maclur 1&1117. * **

  • All r1torcaltl1 1*1ac1 h&Ttq eucleu 1&1117 ttpif tcaaca

tadtcactOtUI of 1a uaaactctpec

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...

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  • S-7 A** mrat lo. ZI, 71, IM, -llf ... .. ,, U1 " ?SfOllt-0001-IR.04

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6.,.2.4.l oa\&r4. . 6.5.2.S . .W..1'!!S

vPAJ) -t. AAy ocher....4'fea of con11dered

.,,ro,r!ace by che Vice ?re11deac

  • o,1rac1oc1.

I* nie plazac rtr* Procecctoc and 1=1'1 .. ecc1a1 procedure*

ac leaac occe per 24 moach1. An ladepeadeac ftre procecc1oa uid 101a pr1v1ncton 1napecc1oa and &\&Clic co be perfoiwed a1mually uctlt11n1 11ch1r qualified otf1ic1 lic1aae1 per101m1l or an oucaid* !tr* proc1cc1oa f irw. 1. AD ic1pecctoa and auclic of che fir* proc1cctoa

&ad 101a pr1v1actoa pro1raa co be p1rf ol"ll9* b' aa o.ac11de f qualif 1" fir* coalVlcuac ac ao 1r1ac1r chua 3 y1ar1. j. lt&cltolo1tcal

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vucae at l1u1 oace per %4 .. cu. 1. The PIOClll CO& flOI, ftOCUll GMI t.rt-*ciq proc1clur1e tor proc1111111

... p&ekacial of radioacc1Te vaac11 ac l1aa1 nee per 24 ....... *

... . Audit °"' , .. ., ........ -4.u1ca11oa 6.J,2.*.2 U..e

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  • a*n*l*irn lndaoj . .i*"oc! uem\luoj .aoiu .. 02 P*Pi.t.e.id
  • q tt*'f* **P***t*a 10 *'aws.:01.i*4

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        • 1 11 -1a*Pl**:c o; tq tTtq1 *z*,*z*,*9 DOl2D*S put 1*,*z*,*i DOllS 02
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  • Ci TT*q* 12iod*c *p*vi12ui1m
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et9tt ao CitltlA/ -.. **-** -*

..... .*** f "-! .!\.1'1-.

6.5.3.5 The Pta1ac Salley and t.ic:1n11c1 scaH shall d1una1ne luue* 11p1Ucuc *eo nuclear sahcy vhich requite* review Pla1ac Revtev

!r=a ieeaa c:on1ider1d Sp1c1ttcac1oa 6.5.l.l.a ehrou1b 4. For eho1e 1e ... noc r1t co PIC, Plane Sat icy anct t.(c:11a1tn1 shall r1c:o*1ncl '4'Ticin1 co pl&AC asana1 ... nc approval or ditapprov&l of tea .. c:oa1tder1ci under 6.5.3.3. l!COIDI of Plaac Saf acy aa4 Lic1a11lll acc1YiC1**

pur1Uaac co Spectf1cac1oa 6.,.l.l be 1ub91cc1ci mcniclll.1 co Pie.* 6.6

.. ) 6.1 SAllTT LIXtr VtOUTtOll 6.7.l Tile followta1 acciou 111&11 be cakn 1a clae Wftl a 1afec7 liail 1* rtolac*1 ** ft* raact-n 111&ll be 1bat * .,..

&H aot raacan* uacil ell* Coillia*1n

  • cllort11a ra..,cioa of o,eracioa (10 era 50.l6(a)(l)(t)(A)). . b. t'!le tdacy Uail nolacioe lball 1te r..-c .. Vic!lia 1 bCNr co ell* C..S**1* ta* acconaacrwtcll 10 en 50.36, u well * ** co tile Ytce
  • hcllU O,Uactou ... co ell* r*&H/li#Jzj.

I c. A,.,. ... 1*1u .** pnpaa4 ta MCoriw* wt.ell 10 Cft*50.l6

          • ol Cilia ., .. iltcact**

Cfte Ml*tJ u.&a nows.. _. cu r.,.n **'1 M nn .... '1 die nc.> cl. t1le , ..... **11 ..........

widda 14 ..,. co die C 'Id* (Sa aouriw* wiell cu r...U-** of 10 C1a *** ), co CM flee Pred .... * .. 1-O,.nc1ou .... 1e 1M . I **:*:..--:* . .. -...... -* 6-10 ..........

J7, 71. 111. i'ff" .............

TSPOllt-OOOl*lll.06

.. '

  • CONTROLS 6.9.3.3 6.10 6.10.l Special Reports a. Spec h 1 Reports sha 11 be submitted to the NRC cover; ng the
  • act1v;t1es identified below pursuant to the requirements of the applicable referenced spaciffcatfons:

Specification Reporting Ref1ranc1 OU1 Area Prestressin9, Anchorage, 4.5.4 Liner and Penetration 4.5.5 Tests 90 Days After Completion of the Test* *A test is considered to be cofl1)1ete after all associated t mechanical, chemical, etc., tests have been completed. . i b. Special reports shall be subllitted in accordance with 10 CFRS0.4, within th* time period specified for each report. _ RECORD BETENJlON . .

  • t_ In addition to th* appl 1cabl.* record retention requirt1111nts of Title { . 10, Code of Federal Regulations, the following records shall be *retained for at least the minilllUll period indicated:

The following records shall.be retained for at least five years: a. Records and logs of fac11tty operatton covering time interval at each pa.er 11v1l. f>. Records and logs of prtnctpal 111intenanc1 act1Y1ttes, inspections, repatr and replacltllftt of principal items* of equiP119nt related to nuclear safety. c. All ,..,ortabl*

1v1nts as defined tn Section 6.4'. t . / *Records of surv1tllanc1 act1Yttt11, tnspecttons and calibrations

' .*.* required.

by th1s1 Technical Spectftcattons.

6*21 Amendment No. ZJ, *-* JJ, ies . . . ...

'I 11

  • ATTACHMENT 3 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED ORGANIZATIONAL TECHNICAL SPECIFICATION CHANGES -REVISION 1 PROPOSED PAGES SUBMITTED IN REVISION 0 (7/15/91)

_MARKED UP TO SHOW REVISIONS December 20, 1991 3 Pages .. ....

  • . AQMINISTRATIVE CQNTROLS 6.4 TRAINING 6.4.r A retraining and replacement training program for the plant staff shall be maintained and shall meet or exceed the requirements and reconrnendations of Section S.S of ANSI NlS.1*1971 and Apoendix "A" of 10 CFR Part SS. 6.4*.2: The Fire Brigade training program shall be maintained and shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975.

Fire brigade training drills shall be held at least quarterly.

.* . 6.5 REVIEW AND AUDIT 6.5.l PLANT REVIEW COHMIUEE lPRCl 6.5.1.1 FUNCTION -The Plant Ravi ew Conni ttee (PRC) sha 11 funct 1 on to . advise the Pl ant General Manager_on all matters related to nuclear safety. . The PRC shal include from the Operations, Radiological Ser ces, Maintenance and Engineering Departments.

The members shall be esignated in administrative procedures by the Plant General . M ager. Jhe Plant General Manager shall also designate the Chairman d Alternate Chairmen in writing. 6.5.1. ALTERNATES Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. No more than two alternates shall participate as voting members at any one time in PRC actfv1ti1s.

"/he fJ""Jli.7ih\

1-,; r P/i't!.

sJ, .. I/ k or . I hi -t!.Y /9NS/. NIP./-J'l7/.

6-5 Amendment No.

J . ADMINJSTRATIYE CONTROLS 6.5.2 NUCLEAR PERFORMANCE ASSESSMENT DEPARTMENT CNPAOl 5.5.2.l FUNCTION The Nuclear Performance Assessment Department (NPAO) shall function I to prov;de independent review of activities in the areas of: a. Nuclear power plant operation

b. Nuclear eng1neer1ng
c. Chemistry and rad1ochem1stry
d. Metallurgy Nflllf .1
  • Instrumentation and control ... at:),__,,,.,,

t G i. Radiological safety h.,.. Mechanical and electrical engineering assurance practices a-.71. -1 6.5.2.2 COHPOSIJION 6.5.2 3 -The NPAD shall include the Director, who reports to the Vice President

-NOD, and a full-time staff of Nuclear Performance

    • Specialists reporting to the Director.

The Director and the .Nuclear Performance Specialists shall meet or exceed the qualifications-*

described in ANSI/ANS 3.1-1987.

The NPAO shall have no direct responsib111t for activities subject to its review. CONSULTANTS .Sf. 'l If suff1c1ent expertise is not available within NPAD to review particular issues, the NPAD shall have the authority to utilize consultants or other qualified organizations for expert advice._ . 6.5 2.4 RESPONSIBILITIES 6.5 2.4.l BEV I EV The NPAO shall review: &*<*Th* safety evaluations for: 1) changes to procedures, equipment

or syst.as, and 2) tests or *experiments completed under the -provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question.
b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59. J:
k.

6-6a Amendment No. JJ, aJ, ** ,

127 .*.* I .

I. * . AOMJNISTRATIYE CONTROLS 6.5.2.4.2 AUDITS (Continued)

f. Any other area of plant operation considered appropriate by NPAD or the Vice President

-Nuclear Operations.

g. The plant Fire Protection Program and implementing procedures at least once per 24 months. h. An independent fire protection and loss prevention inspection and audit to be performed annually utilizing either qualified . _offsite licensee personnel or an fire protection firm. t. An inspection and audit of the fire protection and loss prevention program to be performed by an outside qualified fire consultant at intervals no greater than 3 years. j. Radiological environmental monitoring program and the results thereof at least once per 12 months. k. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures for procusing and packaging of radioactive wastes at once per-24 months. 1. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. Audit reports encompassed by Specification 6.5.2.4.2 above shall be forwarded to the Director NPAD, and Management positions I* -6. 5. 2 .* 4 .3 &.s.i.s responsible for the areas audited within thirty (30) days after completion of the audit. -NPAD revtew of the subjects in Specifications 6.5.2.4 .. 1 and 6.5.2.4.2 shall be performed by an assigned Nuclear Performance Specialist selected on the basis of hts technical expertise . relative to the subject being reviewed.

If the assigned Nuclear Performance Specialist determines the need for interdisciplinary r1vfaw, a coa11tte1 consisting of the Director, NPAO, or his designate, and at least four Performance Spectaltsts, shall The NP shall report to and advise the.Vice President

-NOD of . stgnif cant findings associated with those areas of responsibility spec ted tn Sections 6.5.2.4.1 and Section 6.5.2.4.2.

6-8 Amendment No. JJ, JJ, JJJ, I . ------

l* I _j

  • ATIACHMENT 4 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST -REVISION 1 -Tables of Organization December 20, 1991 4 Pages r . .:.. 11u*s*11 .a.ca ... ...,.aaaeu..,_._.
  • .. I .. ***: I .. * ** a * ..-. ............
  • s411rt a.ca .. a.ca ... .. ... -""*Jtih S..ka ,., ... ace Ira ..... 1 .........

.. .. wrsrt And Construction . *. ; .. : .. :.

... , 1*.110 ,. .. -... ....... ., -* " .; I*--*-**--------

J IWll .n*IJll9 t*ttl*I . *-*-'**ao
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I If .... ,.. .. 1 ... ...,., &*11::. -.us .........

'*...-s ... .. 1* I I I I .

  • I .,... .... 1911 : ..
  • I ' . *: : * .........

' .. i --I . I llM*r .........

llectrlc*l/

IK**tcAl & IK/CCllfPUl*r Civil/ (1191 ... rt .. Stnct11rAl bit-rt .. ... ,Q Ml.DI m1*01* & C.T*TI* *, I .. ...... leKter & , ....... ..,.. ... ltc &It ....... I I I I I lluiM,ler lllD*r Project Accounting bgt ... rl99_ llia111*2nt a fngr.s C.stnc:tloa Adlllai5lr*lioa

' le1tt .. llucle*r Oper*llons Oep*rtment

'c .. struction Org*niz*lion

..... ' "' I. ./.

,, -" F DllKI* "' lllCLDI fllllAEIRl***W*CEE ASSES, .. mA11111111

¥* l Perfo1911ee S,.Cta1tsts Operatt .. s & C...tstl'J

............

Eavlr11111tal Testing ud Procur-nt

i I lncter hi*--* .. lef*lt.. AITA Safet1 Asses-t QualltJ lerlflcatt

.. aM Tratal .. I I I *' i' .. , *** .. ' 'j I Mllalstrattve

... Tread Allalrsts s.ntser .. I . Assessmnt Progr* 5-ntsor Assessors SIO/lm AO CE 11.DG 11£ EP .. ISi ITS II( EE Miii Sf C/f FD lucle*r Operttons Dep*rlmenl

  • -1 lucleAr Perfo111Ance Assessment Dep*rlmenl

_