ML20195D388

Proposed Tech Specs,Revising Title of Positions & Removing Organization Charts

ML20195D388
Person / Time
Site:	Calvert Cliffs
Issue date:	06/13/1988
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20195D380	List: ML20195D375 ML20195D388
References
NUDOCS 8806230110
Download: ML20195D388 (22)

Text

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY............................................'.

6-1 6.2 ORGANIZATION c z.

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6.3 FACILITY STAFF QUAL IFICATIONS.............................

6-6 6.4 T RA I N I N G,.................................................

6 - 6 6.5 REVIEW AND AVOIT 6. 5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

Function................................................

6-6

. Co m po s i t i o n.............................................

6-6 A l t e r n a t e s..............................................

6-6 Meeting Frequency.......................................

6-7

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Qu o r um..................................................

6 - 7 R e s p o n s i b i l i t i e s........................................

6-7 Authority...............................................6-8 Records.................................................6-8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC)

Fu n c t i o n................................................

6 - 8 Co m po s i t i o n.............................................

6 - 9 A l t e r n a t e s..............................................

6-9 Co n s u l t a n t s.............................................

6 - 9 1

Neeting Frequency.......................................

6-9 Qu o r um..................................................

6 - 9 R e v 1 ew..................................................

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A u d i t s..................................................

6-1 1 Authority...............................................

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CALVE,RT CLIFFS'- UNIT 1 XV-Amendment No. 25, 105 8806230110 880613 ADOCK0500g7 PDR P

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6.0 A0ft!NISTRATIVE CONTROLS 6.1' RESPONSIBILITY i

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6.1.1 The Manager k:12:r Oper: tion:= shall be responsible f r overall f operation and shalI delegate in writing the succession to th s responsibkk' tylity during his absence.

1 6.2 ORGANIZATION

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-FACILITY STAFF untT sTM W 6.2.2 The-mm+y a geri::ti:n : hell be es sh;wn r "!gur: 6.?-2 e d :--

a.

Each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room

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when fuel is in the reactor.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

e d.

An individual qualified in radiation protection, procedures shall be on site when fuel is in the reactor, All CORE ALTERATIONS after the initial fuel loadt$g shall be e.

directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this i

operation.

f.

A site Fire Brigade of at least 5 msnbers shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of both units (4 members) or any personnel required for other essential functions during a fire emergency.

a/Mcl1acl 3, S e e, CALVERT OLIFFS - UNIT 1 6-1 Amendment No. 28 NJ,110

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1 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organiutions shall be established for unit operation and corporate management, respectively. The onsite and offsite organiutions shall include the positions for activities affecting the safety of the nuele.1r power plu t.

a.

Lines of authority, responsibility and communication shall be

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established and defined for the highest management levels through 3

intermediate levels to and - including all operating organlution positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional desc*riptions of departmental responsibilitiet, and relationships, and job descriptions for key personnel positloas, or in. equivalent forms of documentation. These requirements shall be documented in FSAR Chapter 12, ar.d updated in accordsnce with 10 CFR 50.71(e).

b.

The Manager - Calvert Cliffs Nuclear Power Plant shall be responsible for overall unit se.fe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c.

The Vice President - Nuclear Energy shall have corporate responsibility for overall plant nuclear safety and shall take any-rneasures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organiutional freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF g.

The General Supervisor - Nuclear Operations, Shift Supervisor and Control Room Supervisor shall hold a senior reactor operator license.

The Control Room Operator shall hold a reactor operator license.

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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS Each member of the facility staff shall meet or exceed the minimum for co:nparatie positions, except for- (1) the 6.3.1 qualifications of ANSI N18.1-1971 Radiation Safety Engineer who shall m Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific i. raining in plant design, and response and analys s ~ of the plant for transients and accidents. 6.4 TRAINING A retraining and replacement training program for the facility staff 6.4.1 shall be maintained under the direction of the General Supervisor - Nuclear Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 53, as applicable. A training program for the Fire Brigade shall be maintained under the 6.4.2 direction of the General Supervisor - Quality Control and Support and shall meet j or exceed the requirements of Section 27 of the NFPA Code-1915. 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COM41TTEE (POSRC) FUNCTION 6.5.1.1 The POSRC shall function to advise the Manager ""cl: r 0; r:ti: : on l all matters related to nuclear safety. i COMPOSITION

6. 5.1. 2 The POSRC shall be composed of the:

^ Managerte!: r 0;:r:tter.:- d a/Md 6/WI Nac/W b l" Chainnan: General Supervisor - 0;;r:ttera /Yueleo.e Operoder4 Member: Member: General Supervisor - Electrical and Controls Member: General Supervisor - Chemistry l Member: General Supervisor - Mechanical Maintenance Member: General Supervisor - Technical Services Engineering l Member: General Supervisor - Radiation Safety l Member: General Supervisor - Plant and Pro, ject Engineering l i ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the POSRC Chairran to serve on a temporary basis; however, no more than two alternates j shall participate as voting members in POSRC activities at any one time. ,ww6 CLIFFS - UHIT 1 6-6 Amendment No. 25,(),5),52,85. 110 I d

2 ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chainnan or his designated alternate. QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chainnan or his designated alternate and four members including alternates. _ RESPONSIBILITIES l 6.5.1.6 The POSRC shall be responsible for: Review of 1) ill procedures required by Specification 6.8 and changes a. thereto, 2) any other proposed procedures or changes thereto as determined by the Managerf-glejrgeg:tgN affectte af,fe t nu; b. Review of all proposed tests and experiments tha. nucinar

safety, Review of all proposed changes to Appendix "A" Technical Specifications.

c. d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. Investigation of all violations of the Technical Specifications includ-e. ing the preparation and forwarding of reports covering evaluation and i recor:cendations to prevent recurrence to the Vice President Nuclear Energy and to the Chainnan of the Off Site Safety Review Comittee. f. Review of all REPORTABLE EVENTS. g. Review of facility operations to detect potential safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review Comittee. i 1. Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee. l j. Review of the Emergency Plan and implementing procedure.s and shall submit recomended changes to the Off Site Safety Review Comittee. k. Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering tvaluation, recomendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to th t Op r: tic = and the Off Site Safety Review comittee. ' Ca4* 1. Review of changes to the PROCESS CONTROL PROGRAM and the 0FFSITE DOSE CALCULATION MANUAL. CALVERT CLIFFS - UNIT 1 6-7 Amendment Na, 26,30,0,H,/)9),110 - - ~--~ - ~

i ADMINISTRATIyECONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Comittee shall: &leetc%ACA6<ke7?..e 3 J a. Recomend to the ManagernNueher-opeca44 ens written approval l or disapproval of items considered under 6.5.1.6(a) through (d)above, b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, Provide written notification within 24 hours to the Vice President-c. Nuclear Energy and the Off Site Safety Review Comittee of disagree-ment between the POSRC and the Mana e ";;h r Op:r:th :t however, the ManagerpNuth:r Opeeat4ons-shal ve responsibility for resolution 6f such disagreements pursuant to 6.1.1 above. (lfvud 6,/f Nac/oe Ser ?hwI a RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each Jneeting and copies shall be provided to the Vice President - Nuclear Energy and Chairman of the l Off Site Safety Review Comittee. 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC) FUNCTION 6.5.2.1 The Off Site Safety Review Comittee shall function to provide independent review and audit of designated activities in the areas of: a. nuclear power plant operations b. nuclear engineering chemistry and radiochemistry c. d. metallurgy and non-destructive examination e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance practices CALVERT CLIFFS - UNIT 1 68 Amendment No, f), 110

ADAINISTRATIVECONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall~be taken in the event a Safety Limit is violated: a. The facility shall be placed in at least HOT STANDBY within one hour, b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President-Nuclear Energy and the OSSRC shall be notified within 24 hours. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Comission, the OSSRC and the Vice President-Nuclear Energy I within 14 days of the violation. 6.8 PROCEDURE _S 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below: i a. The applicable procedures recommended in Appendix "A" of Regulatory Gaide 1.33 Revision 2, February 1978. b. Refueling operations, Surveillance and test activities of safety related, equipment. c. \\ d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program implementation. g. The amount of overtime worked by plant staff members perfonning safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic Letter No. 82-12). h. PROCESS CONTROL PROGRAM implementation. 1. OFFSITE DOSE CALCULATION MANUAL implementation. 6.8.2 Each procedure and administrative policy of 6.8.1 above and changes ehgy f y,W f thereto shall be reviewed by the POSRC and approved by the Manager-i;l::r /s fly Operat4 ens prior to implementation and reviewed periodically as set forth "in put administrative procedures. ,s CALVERT CLIFFS - UNIT 1 6-13 knendment No. 26,4,75.52, 4 5,110 __---_--m-

ADMINISTRATIVE CONTROLS \\ 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: I The intent of the original procedure is not altered. a. b. The change is approved by two members of the plant management staff, at least one of whom holds a fenior Reactor Operator's 4 License on the unit affected. i The change is documented, reviewed by the POSRC and approved by c. the Manager $:hr 0 :=t' = withi,n 14 days of implementation. l dahwt e/If6 Macher hus,- 1%C 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS } l 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement r unless otherwise noted. a STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin 0 shall be submitted following (1) receipt of an operating license (2) g i i 1 amendment to the license involving a planned increase in power level, i (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4)l, or hydraulic perfor-modifications that may have significantly altered the nuclear, therma i J mance of the plant. 6.9.1.2 The startup report shall address each of the' tests identified I in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test l program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report. i ) J 4 i l CALVERT' CLIFFS.- UNIT'1 6 Amendment No. 2p;(3,30 3) A W,110 l 1 4 1 n-. - --_-_n,-,...,n-..- ._,-_.,,n,.n.- ,.n.n. n,, n

ADMINISTRATIVE CONTROLS 1 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Comission prior to implementation. 6.16.2 Licensee initiated changes to the PCP: i 1. Shall be submitted to the Comission in the Semiannual Radioactive i Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: An evaluation supporting the premise that the change did not 4. reduce the overall confomance of the solidified waste product to existing criteria for solid wastes; and b. A reference to the date and the POSRC meeting number in which the change (s) were reviewed and-found acceptable to the POSRC. 2. Shall become effec ManagerY":'--- ~tive upon review by the POSRC and ap 8 5.0'd 57N.lkicAw Sr Sd 0FFSITEDOSECALCbLATIONMANUAL(00CM) 6.17 6.17.1 The ODCM shall be approved by the Comission prior to implementation. 1 1 6.17.2 Licensee initiated changes to the 00CM: l 1. Shall be submitted to the Comission in the Semiannual Radioactive i Effluent Release Report for the period in which the change (s) was I made effective. This submittal shall contain: 4 Sufficient infonnation to support the rationale for the change. a. Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered and i provided with a change number and/or change date together with appropriate analyses or evaluations justifying the change (s); b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and 3 Documentation of the fact that the change has been reviewed c. j and found acceptable by the POSRC. 1 i i 2. Shall becom3 effective upon review by the POSRC and approval of i the Manager-tele:r 0;;r:ti: :. ) (h/w/ O/,Wr ACc/w bwr $v:b 4 t CALYHT'Ct2FFSr-UNIT'l' Sv21;. Amendment-No.17F;198;179, 1 i

..i INDEX ACHINISTRATIVE CONTROLS SECTION PAGE 6.1 R E S P O N S I B I L I T Y.................,.......................... 6-1 6.2 ORGAN!!ATION 6.r.: ^ > >m. m. e49.t.r.C... yp.. M... s..t.r. E..

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6. r. 2. Fe c f.1 i ty Z..' f. NM. T'...-t n1 FE..........................

5-1 FAC IL ITY ST' FF QUAL I FICAT IONS............................. 6-6 6.3 A 6.4 T RA I N I N G.................................................. 6 - 6 6.5 REVIEW ANO AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) Function................................................6-6 Co m p o s i t i o n............................................. 6 - 6 Alternates..............................................6-6 M e e t i n g F r e q u e n cy....................................... 6-7 Quorum'................................................. 6-7 R e s p o n s i b i l I t i e s........................~................ 6-7 Authority...............................................6-8 Records....'............................................6-8 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC) Function................................................ 6-8 j C o m po s i t i o n.............................................. 6 - 9 A l t e r n a t e s.............................................. 6-9 Consultants.............................................6-9 M e e t i n g Fr e qu e n cy....................................... 6 9 0uorum..................................................6-9 Review..................................................6-10 { A u d i t s.................'................................. 6 - 1 1 s A u t ho r i t y............................................... 6-12 l\\ Records................................................. 6-12 g I xy \\ l CALVERT CLIFFS - UNIT 2 Amendment No M/. 86 1

4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY lalmL OGl{s /Jusleae Powe e 'Plu.t 6.1.1 The Manager-Ncks Operstic.; shall be responsible for overall facility operationandshalIdelegateinwritingthesuccessiontothisresponsibility during his absence. 6_. ? ORGANIZATION -4FF-5ue crfs orc nND OND7C OR4RNI ? M 71CA/S b_ _[f.[.! 3.*.[.,5$,$'*N.. ' b. ' I"'IIII/ "'*""W'is"t 'I'd tes'"~'Isil %?? Ort - p., So a ffache/ TACILITY STAF" umr srAff 6.2.2 The fccility Organizatica sha!' bc : thera ca M0're 6_ ?-2 ent-- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. b. At least one licensed Operator shall be in the control room ( when fuel is in the reactor. c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor o shutdown and during recovery from reactor trips. d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. All CORE ALTERATIONS after the initial fuel loa [ing shall be e. ' directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. f. A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of both units (4 members) or any personnel required for other essential functions during a fire emergency. 8 Su aWac Acc/ i CALVERT CLIFFS - UNIT 2 6-1 Amendment No. 26, 93 4 s 1 k

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i 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS Onshe and offsite organizations shall be established for unit operation and corporate managenient, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant, a. Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional dese,riptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in FSAR Chapter 12, and updated in accordance with 10 CFR 50.71(e). b. The Manager - Calvert Cliffs Nuclear Power Plant shall be responsible ~ for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the

plant, c.

The Vice President - Nuclear Energy shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in t operating, maintaining, and providing technical support to the plant to ensure nuclear safety. d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pre >sures. 6.2.2 UNIT STAFF g. The General Supervisor - Nuclear Operations. Shift Supervisor and Control Room Supervisor shall hold a serlor reactor op;rator license. L The Control Room Operator shall hold a reactor operator license. ~

= ou -c of es.e meerd ?i I I rr ia-il c, r~ l y 's ] Wk. Pr Vice Pre.ident Vice PresiAnt Nuclear Energy Elecwic 5.ser-Generna ser c.r e :6.o.ao c-Oper,tian.

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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Nuclear Training l and shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable. 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Quality Control and Support and shall meet l or exceed the requirements of Section 27 of the NFPA Code-1975. 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) FUNCTION 6.5.1.1 The POSRC shall function to advise the Manager-Nucle:r Operation: on l all matters related to nuclear safety. COMPOSITION 6.5.1.2 The POSRC shall be composed of the: Chairman: Manager-Nucle:r Oper: tion: do/w d 6/84 /de/w 70'" "i Member: General Supervisor _0r---tin =s,%c/<ov-No udcxJ r Member: General Supervisor - Electrical and Controls Member: General Superviser - Chemistry Mer.ber: General Supervisor - Mechanical Maintenance l Member: General Supervisor - Technical Services Engineering Member:, Generai Supervisor - Radiation Safety Member: General Supervisor - Plant and Project Engineering l ALTERNATES 6.5.1.3 All alternate menbers shall be appointed in writing *,j the POSRC Chairman to serve on a temporary basis; however, no more t!ian two alternates shall participate as voting members in POSRC activities at any one time. l l CALVERT' CLIFFS - UNIT'2 6 Amendment No. JJ,25,;6;fA,gg; 93 -n

= j i ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month anh as convened by the POSRC Chainnan or his designated alternate. QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chainnan or his designated alternate and four members including alternates. RESPONSIBILITIES. 6.5.1.6 The POSRC shall be responsible for: Review of 1) all procedures required by Specification 6.8 and changes a. thereto, 2) any other proposed determined by the Manager 6"-' procedures or changes thereto as r 0--- "c togffect nuclear safety. l (GIir75 WlHr:2b r:kw 4cs 7Y d b. Review of all proposed tests and experiments that affect nuclear

safety, Review of all proposed changes to Appendix "A" Technical Specifications.

c. d. Review of all proposed changes or modifications to plant systems or - equipment that affect nuclear safety, Investigation of all violations of the Technical Specifications includ-e. ing the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Vice President-Nuclear Energy and to the Chairman of the Off Site Safety Review Comittee. f. Review of all REPORTABLE EVENTS. g. Review of facility operations to detect potential safety hazards. h. Perfonnance of special reviews, investigations or analyses and reports thereon as requested by the Chainnan of the Off Site Safety Review ) Comittee. 1. Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee.

j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Off Site Safety Review Comittee.

k. Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recomendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Mana erdt-! 0 :r:ti:r.: and the Off Site Safety Review Comittee. , a h"k::r jf 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL. CALVERT CLIFFS - UNIT 2 6-7 Amendment No. JJ,75,26,75, Ng,g3

e f l AGMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Comittee shall: Recomend to the Manager...hy:6 GjY6 f..'uc/w (cner lpproval or Q 4wd a.

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3 disapproval of items considered under 6.5.1.6(a) through (d) above, b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (d) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to the Vice President - Nuclear Energy and the Off Site Safety Review Comittee of disagree-ment between the POSRC and the Manage 5:10:r Op:r:tica:; however, the Manager;f'ucl::r Op:r:tica: shal ave responsibility for resolu-tion of suc7r-dingreements, pursuan to 6.1.1 above. -$alue l G// [ G % A W f* k A RECORDS 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Energy and Chairman of the Off Site Safety Review Comittee. l( 6.5.2 0FF SITE SAFETY REVIEW COMMITTEE (OSSRC) FUNCTION 6.5.2.1 The Off Site Safety Review Comittee shall function to provide independent review and audit of designated activities in the areas of: a. . nuclear power plant operations b. nuclear engineering c. chemistry and radiochemistry 1 d. metallurgy and non-destructive examination' e. instrumentation and control f. radiological safety g. mechanical and electrical engineering h. quality assurance practices s CALVERT CLIFFS - UNIT 2 6-8 Amendment No. 26, 93

l ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The facility shall be placed in at least HOT STANDBY within one hour, b. The NRC Operations Center shall be notified by telephone as soon as possible and in all.oses within one hour, The Vice President - Nuclear. Energy and the OSSRC shall be notified within 24 hours. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the POSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation uponfacilitycomponents,systemsorstructures,and(3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Comission, the OSSRC and the Vice President - Nuclear Energy l within 14 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below: The applicable procedures recommended in Appendix "A" of a. Regulatory Guide,1.33, Revision 2. February 1978. b. Refueling operations. Surveillance and test activities of safety related' equipment. c. d. Security Plan implementation, e. Emergency Plan implementation. f. Fire Protection Program implementation. g. The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic Letter No. 82-12). h. PROCESS CONTROL PROGRAM implementat' ion. 1. OFFSITE DOSE CALCULATION MANUAL implementation. 6.8.2 Each procedure and administrative policy of 6.8.1 above and changes thereto shall be reviewed by the POSRC and approved by the Manager Oper: tier.: prior to implementation and reviewed periodically as se orth in ## administrative procedures. <p ' CALVERT CLIFFS - UNIT 2 6-13 Amendment No.JJ,25,55,55,26,93 ,+ w c w re- -~ -e e a

ADMINISTRATIVE CONTROLS 6.8.3 ' Temporary changes to procedures of 6.8.1 above may be made pro-vided: a. The intent of the original procedure is not altered. b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, The change p : documented, reviewed by the POSRC and aooroved by c. the Manager k le:r Oper: tier.: within 14 dayh/.wrof jmplementation. da tvv b GS47s A'a c /d lL-ee 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6,9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted. STARTUP REPORT ( 6.9.1.1 A sumary report of plant startup snd power escalation testin shall be submitted following (1) receipt of an operating license. (2) g amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant. 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the c 'trating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and speci fications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. CALVERT CLIFFS - UNIT 2 6-14 Amendment' No. JA,26,55,75. M..' 93 i y- --r.-

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l,. ADMfNISTRATi'!c CONTROLS 6.16 PROCE55 CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the CecTnission prior to implementation. l 6.16.2 Licensee initiated changes to the PCP: l 1. Shall be submitted to the Commission in the Semiannual Radicactive Effluent Release Report for the period in which the enange(s) was made. This submittal shall contain: An evaluation supporting the premise that the change did a. not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and b. A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to the POSRC. 2. Shall become effective upon review by the POSRC and approval of ,fg bei,. ?c v lh $ 6.17 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.17.1 The 0001 shall be approved by the Comission prior to implementation. l 6.17.2 Licersee initiated changes to the 00CM: f 1. Srall be submitted to 'the Comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: Sufficient information to support the rationale for the a. change. Infonnation submitted should consist of a package of those pages of the 00CM to be changed with each page ntsnbered and provided with a change number and/or change date together with appro justifying the change (s)priate analyses or evaluations b. A determination that the ch.nge will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been reviewed c. and found acceptable by tha POSRC, 2. Shall become effective upon review by the POSRC and approval,of the Managerucic:r C;;cr:ti_.... da/w / W M, nuJ w-R<.e 7/w CADERTCLIFFH-UNIT 21 6-227 Amendment'No. 86.77',93',-96. i e. o w ,,---,.,--w. --}}