ML20082T244

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Amends 161 & 141 to Licenses DPR-53 & DPR-69,respectively, Changing Specific Titles of Managers Throughout TS Section 6.0,administrative Controls,To Be Consistent W/Organization of Util at Calvert Cliffs Facilities as of 901001
ML20082T244
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/11/1991
From: Capra R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20082T248 List:
References
NUDOCS 9109180169
Download: ML20082T244 (47)
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Text

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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 60-317 CALVERT Cliffs NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY 0PERATING L_ICENSE Amendment No.161 License No. OPR-53 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Baltimore Gas and Electric Company (the licensee) dated August 23, 1990, as supplemented on September 28, 1990 and June 28, 1991, complies with the standards andrequirementsoftheAtomicEnergyActof1954,asamended(the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1: B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities tuthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to.the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. OPR-53 is hereby amended to read as follows: 1 9109100169 910911 PDR ADOCK 05000317 P PDR r

[ o ,p, i i (2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.161. are herebyIncorporatedinthelicense. The licensee shall i operate the facility in accordance with the Technical i Specifications. 3 This license amendment is effective as of the date of its issuante and shall be implemented within 30 days, TOR THE NUCLEAR REGULATORY COMMISSION Y TSdD. Of Robert A. Capra, Director Project Directorate 1-1 Division of heactor projects - 1/II Office of Nuclear Reactor Regulation l l

Attachment:

Changes to the Technical Specifications Date of Issuance: September 11, 1991 i l i

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= [' UNITED STATES 3 I $+' / -i NUCLEAR REGULATORY COMMISSION edi! wAsniNotoN, o c. aus 's,,,e* BALTIMORE GAS AND El.ECTRIC COMPANY DOCKET NO. 50-318 CALVERT Cliffs NUCLEAR POWER PL ANT, !! Nil NO. 2 AMENDMENT TO TACILITY OPERATING LICENSE Amendment No. 141 License No. DpR-69

1..

The Nuclear Regulatory Commission (the Connission) has found that: A. The application for amendment by Baltimore Gas and Electric Company (the licensee) dated August 23, 1990, as supplemented on September 28, 1990, and June 28, 1991, complies with the standards and requirements of the Atomic Energy Act of ',954, as amended (the Act) and the Commission's rules and retch :fons set forth in 10 CER Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (di) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CfR part 51 of the Commission's regulations and all applicable requirements h N been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of facility Operating License No. DpR-69 is hereby amended to read as follows: -n-m-

L ) n i i f -2 I f (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.141, are hereby incorporated in the license. he licensee shall operate the facility in accordance with the Technical i Specifications. [ 3. This license amendment is effective as of the date of its issuance and shall be implen,ented within 30 days. i FOR THE NUCLEAR REGULATORY LOMMISSION T U O-.0 W Robert A. Capra, Director ( Pro.iect Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of Issuance: September 11, 1991 [ t i i l t I h i r -s--.. y -,,,,,,.~ _ - -,,w,, ,..y-y.,,w y-A -e

a ATTACWNENT-TO LICENSE AMINDMENTS ANENDNENT NO.. tst rACILITY.0PERATING l! CENSE.h0. 0PR-53 AMENDNINT.NO.141. FAClllTY-0PERATING llCENSE -NO, -DPR-69 p0CKET-Eqs.50317tvP50-2:3 Revise Appendix A as follows:- Remove Pages Insert Pages 6-1 6-1 6-la 6-la 6-6 6-6 6-7 6-7 6-7a 6e 6-8 6-8 6-8a 6-8b 6 69 6, 6-10 6-10 6 11 6-11 6-12 6-12 6-13 6-13 6-13a 6-13a 6-14 6-14 6-15* 6-15* 6 19* 6-19* 6 20 6 20-6-21* 6 21* 6 22 6-22

  • Pages that did not change, but are overleaf.

k b ADMINISTRAVIVE CONTROLS R RESPONSIBILITY 6.1,1 The Plant General Manager shall be responsible for overall l facility. operation and shall delegate in writing the succession to this responsibility during his absence. t 6.2 ORGANIZATION 6.2.1 ONSITE & OFFSITE ORGANIZATIONS I i Onsite and offsite organizations shall be esn bitshed for unit l operation and corporate management, respectivtiv. The onsite and offsite organizations s'iall include the positions for activities affecting the safety of the nuclear power plant. j 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 i organization positions. These relationships shall be l documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key persoi:nel ' positions, or in equivalent forms of i documentatien. These requirements shall be documented in'FSAR t Chapter 12, and updated in accordance with 10 CFR 50.71(e), t b. The Plant General Manager shall be responsible for overall unit l 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 i responsibility for overall p1Lnt nuclear safety and shall take 3 any measures needed to ensure acceptable performance of the l staff in operating, maintaining, and providing technical l support to the plant to ensure nuclear safety. j d. The individhitir he ' sin the operating staff and those who i carry out heal-e phys.cs and quality assurance functions may t report to the-appropriate onsite manager; however, they shall i have sufficient organizational feedom to ensure their ) -independence from operating pressures, j 6.2.2 UNIT STAFF - f a. Each on duty shift shall be composed of at lea * ' the minimum i shift crew composition shown in Tabis 6.2-1. l 1 b. A+. least one licensed Operator shall be in the control room when fuel (s in the reactor. y i Effective at 12:01..m. on November 30, 1988. Replaces page 6-1(t). } ) CALVERT CLIFFF - UNIT 1 6-1 Amendment No. JE/9/JJS/UJ,161!

BDMINISIF#LVLf0MIR0LS 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, d, An individual qualified in radiation protection procedures shall be on site when fuel is in the react e. All CORE ALTERATIONS af ter tne initial fuel loading shall be 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, g. The Superinter. dent-Nurlear Operations shal'i hold or have held a senior reactor operator license at Calvert Cliffs. The General inpervisor Nuclear Plant Operations, Shift Supervisor and t.ontrol Room Supervisor shall hold a senior reactor operator license. The Control Room Operator shall hold a reactor operator license, l CALVERT Cliffs - UNIT 1 6-la Amendment No. JE/f)/JJ,0/JJJ/JEE, 161 a

e 4 AQ!ill(ISTRAllyLCDNTRQLS 6.3 FACILITY STAFF OUAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications 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 Shif t 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 TRAININ(i 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 and shall meet or exceet the requirements and recommendations 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-Planning and Support and shall l meet or exceed the requirements of Section 27 of the NFPA Code-1975. 6.5 REVl[W AND AUDIT E.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) FUN (J10H 6.5.1.1 The POSRC shall function to advise the Plant General Manager on l all matters related to nuclear safety. COMPOSITION 6.5.1.2 The POSRC shall be composed of at least seven, but no more than ten, members, including the Chairman. Members shall collectively have experience in the following areas: Nuclear Operations Electrical and Controls Maintenance Chemistry Mechanical Maintenance Nuclear Engineering Radiation Safety Plant Engineering Design Engineering Members shall be appointed in writing by the Plant General Manager. Members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience. At least one member shall have an SR0 license on Calvert Cliffs Units 1 and 2 CALVERT CLIFFS - UNIT 1 6-6 Amendment No. / Elf 3/EE/E//EE/ IJE/lli,161

i ) 4 M!ilNISTRATIVE CONTROLS i i - CHAIRMAN [ 6.5.1.3 The Chairman and alterr. ate Chairmen of the POSRC shall be appointed in writing by the Plant General Manager. Chairmen shall have a minimum of 10 years power plant experience of which a minimum of-three years shall be nuclear power experience, j ALTERNATES i 6.5.1.4 All alternate members shall be appointed in writing by the Plant General Manager. Alternate members shall have a minimum of eight years [ power plant experience of wM:h a minimum of three years shall be nuclear l power experience. MEETING FRE00ENCY 6.5.1.5 The POSRC shall meet at least once per calendar month and as I convened by the POSRC Chairman or one of-the designated alternates, j QUDfWB l a 6.5.1.6 A quorum of the POSRC shall include the Chairman or one of the l - designated alternate chairmen and shall consist of a ma,jority of the members, including alternates. No more than half of the quorum shall be { alternates', including an alternate chairman. { RESPONSIBILITIES 6.5.1.7 _The P0 RC shall be responsible for the following except for i those items-designated for review by the Procedure Review Committee or Qualified Reviewer in accordance with Specification 6.5.2 and 6.5.3, - respectively: a. Review of 1) all procedures required by Specification 6.8 and changes thereto,-and 2)-any other proposed procedures _or changes thereto as determined by the Plant General Manager to affect nuclear safety. Cross-disciplinary reviews of these procedurec are conducted in accordance with administrative procedures in addition to the reviews conducted by POSRC. the Procedure Review Committee, or-l Qualified Reviewer. t b. Review of all proposed tests and experiments that affect j nuclear safety. c. Review of all proposed changes to Appendix."A" Technical l Specifications. d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. CALVERT CLIFFS - UNIT 1 6-7 Amendment No. /E/JE/fJ/9f/JPE/--F 119/171,161 l I .4-

l l-ADMINISTRATIVE CONTRQLS e. Review of the Plant Security Plan and implementing procedures l and shall submit recommended changes to the Off-Site Safety Review Committee. -f. Review of the Emergency Plan and implementing procedures and l shall submit recommended changes to the Off-Site Safety Review Committee. g. Review of changes to the PU 'ESS CONTROL PROGRAM and the 0FFSITE DOSE CALCULATION MANUAL. h. Review of all 10 CFR 50.59 Safety Evaluations that support procedures in 6.5.1.7.a and changes or modifications in 6.5.1.7.d. 1. Investigation of all violations of the Technical Specifications l including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Plant General Manager, the Vice President Nuclear Energy and to l i the Chairman of the Off-Site Safety Review Committee. j. Review of all REPORTABLE EVENTS. l -k. Review of facility operations to detect potential safety l hazards. 1. Review of any accidental, unplanned or uncontrolled radioactive l 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, recommendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Plant General Manager and the Off-Site l Safety Review Committee, m. Performance of special reviews, investigations or analyses and l reports thereon as requested by the Chairman of the Off-Site Safety Review Committee. CALVERT CLIFFS - UNIT 1 6-7a Amendment No. 29/J9/f3/Sf/J9E/ 119/131,161

t -ADMINISTRATIVE CONTROLS [ -AUTHORITY f 6,5.1.8 The Plant 0perations and Safety Review Committee shall: a. Recommend to'the approval authority approval or disapproval of } . procedures considered under 6.5.1.7.a. j s b. Recommend to the Plant General Manager approval or disapproval of items considered under 6.5.1.7(b) through (h) above. c. Render determinations in writing with regard to whether or not each item considered under 6.5.1.7(a) through (h) above l constitutes an unreviewed safety question. [ d. Evaluate root causes and recommended actions to prevent recurrence _for items considered under 6.5.1.7(1) through (1). e. Provide writ.en notification within 24 hours to the Vice- -President-Nuclear Energy and the Chairman of the Off-Site Safety Review Committee of disagreement between the POSRC and the responsible approval authority in the case of item 6.5.1.7.a or between the POSRC and the Plant General I Manager;- however, the P1 ant General llanager shall have responsibility for resolution of -such disagreements pursuant to 6.1.1 above. -RECORDS j 6.5.1.9 The POSRC shall maintain written minutes of each meeting and l -copies shall be provided to the_Vice President-Nuclear Energy, Chairman of-the Off-Site Safety Review Committee, and the Plant General Manager, l { 6.5.2 PROCEDURE REVIEW COMMITTEE l FUNCTION [ \\ L 6.5.2.1 The Procedure Review Committee may function to review items listed in Specification 6.5.1.7(a) in lieu of review by POSRC or Qualified Reviewer as directed by the Plant General Manager. i L t COMPOSITION l l l. 6.5.2.2 The Procedure Review Committee shall be composed of a Chairman i .and eight individuals who shall collectively have expertise in the areas i contained in Technical-Specification 6.5.1.2. l ) I t CALVERT CLIFFS - UNIT 1 6-8 Amendment No. AJ/JJS/JJJ,161 r I

f ACHINISTR&ll1LCBNTROLS - Members'shall be appointed in writing by the Plant General Manager, Members shall have a minimum of eight years power plant experience of which a minimum of three years shal1~be nuclear power experience. At j least one member shall be a POSRC member or alternate. The charter for the-Procedure Review Committee shall include a description of membership, qualifications, functions, and reports and shall be described in plant administrative procedures.. The Procedure Review Committee may be dissolved at the discretion of the Plant General Manager, j CHAIRMAN 6.5.2.3-1he Chairman and alternate Chairmen of the Procedure Review Committee shall be appointed in writing by the Plant General Manager. Chairmen shall have a minimum of eight -years power plant experience of r which a minimum of three years shall be nuclear, power experience. ALTERNATES-6.5.2.4 All alternate-members shall be appointed.in writing by the Plant General Manager. Alternate members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience, f -MEETING FRE0VENCY 6.5.2.5 The Procedur0 Review Committee shall meet at_least once per calendar month and as convened by the Chairman or his designated alternates. -j OVORUM i I 6.5.2.6 A quorum for the Procedure Review Committee shall consist-of the r Chairman _or one of the designated alternate Chairmen and three primary or t alternate members provided at least four disciplines are represented. l AUTHORITY t - 7 6.5'2.7 The Procedure Review Committee shall:_ i a. Recommend to the Approval Authority approval or disapproval of I L procedures considered under 6.5.1.7(a). s b. Render determinations in writing with regard to whether or not l each procedure under 6.5.1=7(a) constitutes an unreviewed safety question. t c. Provide written notification within 24 hours to the Vice President-Nuclear? Energy and the Chairman of_ the Off-Site Safety Review Committee of disagreements between the Procedure Review Committee and the responsible approval authority. The j Plant General Manager shall have responsibility for resolution j of such disagreements pursuant to 6.1.1 above. l i l i CALVERT CLIFFS - UNIT 1 6-Ba Amendment No.161 j 1 i

} ADMINISTRATIVE CONTROLS o RECORDS j 6.5.2.8 The Procedure Review Committee shall maintain written minutes of i each meeting and copies shall be provided to the Plant General Manager. l 1 6.5.3 OVAllFIED REVIEWERS j FUNCTION lA 6.5.3.1 The Plant General Manager may designate specific procedures or l classes of procedures described in Specification 6.5.1.7.a to be reviewed i by Qualified Reviewers in lieu of review by POSRC or the Mced:tre Review Committee, i -AUTHORITY l 6.5.3.2 Qualified Reviewers shall: -a. Recommend-to the approval authority approval cr disapproval of designated procedures and changes considered urader 6.5.1.7'a, and j b. Render determination in writing with regard to whether or not each procedure-under 6.5.1.7.a constitutes an unreviewed s safety question. c. Provide written notification within 24 hours to the Vice President-Nuclear Energy and the Chairman of the Off-Site Safety Review Committee of disagreements between the-Qualified Reviewer and the approval _ authority. The Plant General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1. above. j CERTIFICATION .6.5.3.3-Qualified Reviewers shall be nominated, trained, and certified i in accordance with administrative proceduresi. Certification shall be by a department manager. t 6.5.3.4 Certification requirements of personnel-des.lgnated as Qualified ? Reviewers shall' be in accordance with administrative procedures, ' ? l L t L I L A f I i ( i l CALVERT CLIFFS - UNIT 1 6-8b Amendment No., 161 e h

s. v ADMINISTRATIVE CONJROLS ^ Qualified Reviewers shall have; t a.. A Bachelors degree in engineering, related science, or technical discipline, and two-years of nuclear power plant experience; DB b. Six years of nuclear power plant experience i DE c. Equivalent combination of education and experience.as approved I by a Department Manager. t RECORDS 6.5.3.5 Review of procedures by Qualified Reviewers shall be documented-in accordance with administrative procedures. l -6.5.4 -0FF-SITE SAFETY REVIEW COMMITTEE (OSSRC) l FUNCTION [ 6.5.4.1 The Off-Site Safety Review Committee shall functi_on-to provide l independent review and audit of designated activities in the areas of: a. nuclear power plant operations 1 b. nuclear engineering t lc. chemistry and radiochemistry [ f d. . metallurgy and non-destructive examination f e. instrumentation and control j s radiological safety i f. g. mechanical and electrical er.gineering h.- quality assurance practices j s s u ? i -[ i l l I i CALVERT CLIFFS - UNIT 1 6-8c Amendment No.161 i i l-r ... e

c .g. t, ADMINISTRATIVE CONTR0ls COMPOSITION- ] [ 6.5.4.2 The OSSRC shall' be composed of at least seven members,10cluding tho Chairman. Members of the OSSRC may be from the Nuclear Entrg* Division or other BG&E organization or from organizations extert.0 to BG&E and shall collectively have expertise in all of the areas of 6.5.4.1. I f 0VAllflCATIO% 6.5.4.3: The Chairman, members and alternate members of the OSSRC shall .l be appointed in writing by the Vice President-Nuclear Energy and shall have an academic degree in engineering or a physical science, or the-equivalent, and in addition shall have-a minimum of five' years technical j experience in one or more areas given in 6.5.4.1. No more than two l alternates shall participate as voting members in OSSRC activities at any one time. CONSULTANTS 6.5.4.4 Consultants shall be utilized as determined by the OSSRC l Chairman to provide expert advice to the OSSRC. l t -{ MEETING FRE0VENCY 6.5.4.5.The _0SSRC shall meet at least once per six months. l { OUORUM 6.5.4.6 -The quorum of the OSSRC necessary for the performance of the l OSSRC review and audit functions of these Technical Specifications shall l L consist of more than half the OSSRC membership or at least four members, . whichever is greater, -This quorum shall include the Chairman or his appointed alternatetand the OSSRC members, including appointed l alternates, meeting the-requirements of Specification 6.5.4,3. No more than a minority of the quorum shall have line responsibility for operation of.the' plant. I i L L l i ? 1 CALVERT CLIFFS - UNIT 1 6-9 Amendment NJ. #/JJE,161 i i .4~ ../ .-.-. a

' ADMINISTRATIVE CONTROLS. f REVIEW 6.5.4.7 The OSSRC shall review: - 1 a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the i provisions of Section 50.59, 10 CFR, to verify that such L actions did not constitute an unreviewed safety question, i b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. { c. Proposed tests or experiments which involve an unreviewed I safety question as defined in Section 50.59, 10 CFR. d. Proposed changes in Technical Specifications or this Operating License. l e. Violation of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures i or instructions having nuclear safety significance, f. Significant operating abnormalities or deviatiors from normal and expected performance of plant equipment that affect nuclear

safety, j

i g. All REPORTABLE EVENTS. - L h. All recognized indications.of-an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components. j i. Reports and meetings minutes of the POSRC. r i .. i - i 9 i i .I CALVERT CLIFFS -UNIT 1 6-10 Amendment No. #,161 I ~ ,y.

4 @MINISTRATiVE CONTROLS A@lli 6.5.4.8.1 Audits' of facility activities shall be performed under the l cognizance of the OSSRC. These audits shall encoropass: a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b. The performance, training and goalification of the entire facility staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in facility equipment,. structures, systems or method of operation that affect nuclear safety at least once per 6

months, d.

The performance of activities required by the Quality Assurance Program tu meet the criteria of Appendix "B", 10 CFR Part 50, at least once per 24 months, e.

Deleted, f.

- The Safeguards Contingency Plan and implementing procedures at least~once per 12 months in accordance with 10-CFR 7:.40(d). g. Any other area-of facility operation-considered appropriate by the OSSRC or the Vice President-Nuclear Energy, h. The Facility Fire Protection Program and implementing -procedures at least once per 24 months. i. An independent fire protect _ ion and loss prevention program-inspection and audit shall be performed at-least once per 12 months utilizing.either qualified offsite licensee personnel or an outside fire protection firm. j. An inspection and audit of the fire protection and loss prevention program-shall be performed by a qualified outside fire. consultant at least once per 36 months. k._ _The radiological environmental monitoring program and the results thereof at-least-once per 12 months. 1. The OFFSITE_ DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months, m. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. CALVERT CLIFFS - UNIT 1 6-11 Amendment No. /E/E//J9E/JJE,161

ADMINISTRATIVE CONTROLS n._ -The performance of activities required by The Quality Assurance Program for effluent and environmental monitoring at least once per 12 months. 6.5.4.8.2 Review of facility activities shall be performed under the l cognizance of the OSSRC. These reviews shall encompass: a. The Facility Emergency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR Part 50.54(t). Mitt 0H111 6.5.4.9 The OSSRC shall report to and advise the Vice President-Nuclear Energy on those areas of responsibility specified in Section 6.5.4.7 and 6.5.4.8. RECORDS 6.5.4.10 Records of OSSRC activities shall be prepared, approved and l-distributed as indicated below: a. Minutes of each OSSRC meeting shall be prepared, approved and forwarded to the.Vice President-Nuclear Energy within 14 days following each meeting, b. Reports of reviews encompassed by Section 6.5.4.7 above, shall l be prepared,-approved and forwarded to the Vice President-Nuclear Energy within '14 days following completion of-the

review, c.

Audit reports encompassed.by Section 6.5.4.8 ebove, shall be l forwarded to the Vice President-Nuclear Energy and to the management positions responsible for the -areas. audited within 30 days after completion of the audit. 6,6-REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: a. The Commission shall be notified and a report submitted pursuant to the requirements-of-Section 50.73 to 10 CFR-Part 50, and b. Each REPORTABLE EVENT shall be reviewed by the POSRC and the -results of this review shall be submitted to the OSSRC and the Vice President-Nuclear Energy. CALVERT CLIFFS - UNIT 1 6-12 Amendment No. /S/EZ/Sf/JSE/JJS,16! L

ADMINISTRATIVLCONTROLS -6.7 SAFETY LIMIT VIOLATIpH 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 i President-Nuclear Energy and the OSSRC shall.be notified within 24 hours. la c. A Safety Limit Violation Report shall be prepared.. The report shall be reviewed by the POSRC. This report shall describe (1) l applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent J recurrence. d. The Safety Limit Violation Report shall be submitted = to the Commission, the OSSRC and the Vice President-Nuclear Energy: within 14 days of the violation. 6.8 PROCEDURES j -t 6.8.1 Written procedures shall be established, implemented and-l maintained covering the activities referenced below: j s a.- The applicable procedures. recommended in Appendix "A" of l Regulatory Guide 1.33, Revision 2, February 1978, b. Refueling operations, c '. -. Surveillance and test' activities of safety related equipment. d. Security Plan implementation. f e. Emergency Plan implementation. l 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 l NRC Policy Statement on working Hours (Generic Letter No.-- [ 82-12). l t POSRC.is only' required to review Fire Protection procedures and j changes thereto which affect nuclear safety. j I CALVERT CLIFFS - UNIT 1 6 13 Amendment No. J$/fJ//J/EJ/JSJ/ 119/l}l,161 ? - + - ., _ ~, - - -v.,

i ^ ? gDMINISTRATIVECONTROLS h.- ' PROCESS CONTROL PROGRAM implementation. i.. OFFSITE DOSE CALCULATION MANUAL implementation. l 6,8.2 The Plant General Manager may designate saecific procedures or classes of procedures in writing to be reviewed ay the Procedure Review Committee or by Qualified Reviewers in !ieu of review by the POSRC. -l Review by the Procedure Review Committee shall be in accordance with t paragraph 6.5.2. Review by Qualified-Reviewers shall be in accordance with paragraph 6.5.3. j 6.8.3 Procedures listed in 6.8.1 shall be approved by the Plant General-Manager or by cognizant Managers, Superintendents, or General Supervisors l (or Directors) that report directly to a Manager prior to implementation. i as specified by. administrative requirements. The approval authority for i specific procedures or classes of procedures shall be designated in writing by the Plant General Manager and shall be a different individual from the Qualified Reviewer. t 6.8.4 Each procedure of 6.8.1 above and changes thereto shall be -l l reviewed periodically as set forth in administrative procedures, i -t i 5 [ i ? i f r I i CALVERT CLIFFS - UNIT 1 6-13a Amendment No. JElf3//E/E//ipE/ 119/1}]'161 i'

E .l MMNISTRATIVE CONTROLS f 6,8.5 Temporary changes to procedures of 6.8.1 above may-be made _l l .provided:: a a. 1The intent of the original procedure is not altered. b. The change is approved by two members of the plant management j staff,:at least one of whom holds a Senior Reactor Operator's i License on_the unit affected, c. The change is documented, reviewed by the POSRC, the Procedure Review Committee,Tr by a Qualified Reviewer and approved by i the' designated approval authority within 14 days of f implementation, i 6,9 REPORTING RE0VIREMENTS i ROVIINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10,- ll Code of Federal Regulations, the following reports shall be submitted to-the Director of the Regional Office of Inspection and Enforcement unless j otherwise noted. [ f STARTUP REPORT i 6.9.1.11 A summary report of plant startup and ~ power escalation testing l shall be submitted following (1) receipt of an operating license, (2) -1 amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by;a different fuel suoplier, and'(4) modifications that may have i significantly altered.the nuclear, thermal,- or hydraulic performance of -l the-plant. i -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 -l operating conditions-or characteristics-obtained during the test program and a comparison of =these values with ' design predictions and specifications. Any. corrective actions that were required to-obtain i satisfactory operation shall also be described. Any additional specific

details required-in license conditions based on other commitments shall be included in this report.

i L -t ? t i s CALVERT CLIFFS - UNIT 1 6-14 Amendment No. 29/f3/E//JA/JEE/ t! 119/lil,161 l ~i l f L . r.

AQMJHISTRATIVE CDNTROLS r. 6.9.1.3-Startup reports shall be. submitted within (1) 90 days following

completidn-of the startup test program, (2) 90 days following resumption

= -or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever_is earliest. If the Startup Report.does not cover all_three events (i.e., initial criticality, completion of-startup test program, and resumption or commencement of commercial power ' operation), supplementary reports shall be submitted at least every three-months until all three events have been completed. ANNUAL REPORTSE 6.9.1.4 Annual reports covering the activities of the unit as described below for-the previous calendar year shall be submitted prior to March 1 ~ of.each year. The initial report shall be submitted prior to March 1 of-the year following initial criticality. - 6.9.1.5 Reports required on an annual basis shall include:' -a.- . A tabulation on-an annual basis of the number of station, utility,:and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their a exposure according to work and job. functions, 'ggociated man. rem d-e.g.,-reactor operations and-_ surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.: The. dose assignment to various duty functions may be estimates based on pocket dosimeter, llD, _ or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be' accounted for. In- _the aggregate, at least.80% of the total whole body dose received.from external' sources shall be assigned to specific major work functions. b. The complete results of steam generator tube inservice inspections performed._ddring the report period (reference Specification 4.4.5.5 b). -c. . Documentation of all failures and challenges to _the pressurizer PORVs or safety valves. 4. JZ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station. 2Z This tabulation supplements the _ requirements of 10 CFR Part 20.407. CALVERT CLIFFS - UNIT 1 6-15 Amendment No. #,AA

~~ ~_ ~_- -- SM INISTRATIVE CONTROLS t 6.10 RECORD RETENTION 6.10.1 - The following records shall be retained for at' least five years; a. Records and logs of facility operation covering time interval f at each power level. l 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. d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. e. Records of reactor-tests and experiments.- f. Records of changes made to Operating Procedures, .i g. Records of radioactive shipments. 1 h. Records of sealed source and fission detector leak tests and results. 1 i, Records'of annual physical inventory of all sealed source material of record. 6.10.2 The following records shall be retained for the dcration of the j Facility-0perating License: .a. Records and drawing changes reflecting facility design modifications made to systems and equipment. described in the ' Final Safety Analysis Report. b. Records of new and irradiated fuel inventory, fuel transfers i and assembly burnup histories. c. Records of facility radiation and contamination surveys. i i I i i t i i Le CALVERT CLIFFS - UNIT 1 6-19 Amendment No. ES,SA l i r ef.,

MM NISTRAT1YLCMIRQLS j d. Records of radiation exposure for all individuals entering radiation control areas, e. Records of gaseous and liquid radioactive material released to the environs, f. Records of transient or operational cycles for those facility I components identified in Table 5.7-1. g. Records of training and qualification for current members of the plant staff. h. Records of in-service inspections performed pursuant to these Technical Specifications. i. Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records. j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. k. Records of meetings of the POSRC, the Procedure Review Committee, and the OSSRC, 1. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13. m. Records of the service lives of all safety related snubbers including the date at which the service life commences and associated installation and maintenance records. 6.11 RADI ATION PROTECTION PROGRAJ Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20: a. A high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area. CALVERT CLIFFS - UNIT 1 6-20 Amendment No. E,4/L2E,161 J

l s a f MilNISTRATIVE CONTRO15 b. A high radiation area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1.a, above, and in addition locked barricades shall be prcrided to prevent unauthorized entry into such areas and the keys shall be maintained by the Supervisor Radiation Control Operations and the Operations Shift Supervisor on duty under their separate administrative control 6.13 SYSTEM INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following: 1. Provisions establishing preventive maintenance and periodic visual inspe: tion requirements, and 2. Leak test requirements for each syste.. at a frequency not to exceed refueling cycle intervals. 6.14 10 DINE MONITORING The licensee shall implement a program which will ensure the capability l to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following: 1. Training of personnel, 2. Procedures for monitoring, and 3. Provisions for maintenance of sampling and analysis equipment. 6.15 POST ACCIDENT SAMPLING The licensee shall establish, implement and maintain a program

  • which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphe.

samples under accident conditions. The program shall include the following: 1. Training of personnel, 2. Procedures for sampling and analysis, and 3. Provisions for maintenance of sampling and analysis equipment. It is acceptable if the licensee maintains details of the program in plant operation manuals (e.g., chemistry procedures, training instructions, maintenance procedures, ERPIPs). CALVERT CLIFFS - UNIT 1 6-21 pf#f/JE/74/ED//M//E3/9E/JEE, Am. No. JEE/JJp,ll3

_s ADMINISTRATIVE-CONTROLS 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to l implementation, j I 6.16.2 Licensee initiated changes to th? PCP:. 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the 5 change (s) was made. This submittal shall contain I a. An evaluation supporting the premise that the change did not reduce the overall conformance of the solidified waste i product to existing criteria for solid wastes; and j b. A reference to the date and the POSRC meeting number in I which the change (s) were reviewed and found t.cceptable to i the POSRC. f 2. Shall become effective upon review by the POSRC and approval of the Plant General Manager. l l 6.17 0FFSLTE DOSE CALCULATION HANUAL (00CN) 6.17.1 The ODCM shall be approved by-the Commission prior to implementation. I 6.17.2 Licensee initiated changes to the ODCM: [ 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: 7 a. Sufficient information-to support the rationale for the change..Information: submitted should consist of a package of those.pages of the ODCM to be changed with each page numbered and provided with a change number and/or change date together with appropriate analyses or evaluations i justifying the change (s); j b. A determination that the change will not reduce the i accuracy or reliability of dose calculations or setpoint. determinations; and c. Documentation of the fact that the change has been reviewed and found acceptable by the POSRC. 2. Shall become effective upon review by the POSRC and approval of i the Plant General Manager. l. l l l L L l CALVERT CLIFFS - UNIT 1 6-22 Amendment No. JEE/JES/JJE/JJJ/ I JJJ.161 u

ADMINISTRATIVE CONTROLS 6.1 RESP _QNSIBillTY 6.1.1 The Plant General Manager shall be responsible for overall l facility operation and shall delegate in writing the succession to this responsibility during his absence. 6.2 ORGANIZATION 6.2.1 QNSITE & OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, 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 comrounication 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 descriptions 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 plant General Manager shall be responsible for overall " nit l safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of de 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 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 pressures. 6.2.2 UNIT STAFF 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. Effective at 12:01 a.m. on November 30, 1988. Replaces page 6-1(t). CALVERT CLIFFS - UNIT 2 6-1 Amendment No. /E/#/JJJ,161 /

BDMINISTRATJVE CONTROLS 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, d, An individual qualified in radiation protection procedures shall be cn site when fuel is in the reactor, e. All CORE ALTERAflCNS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent rr ponsibilities 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. g. The Superintendent-Nuclear Operations shall hold or have held a senior reactor operator license at Calvert Cliffs. The General Supervisor-Nuclecr Plant bperations, Shif t Supervisor and Control Room Supervisor shall hold a senior reactor operator license. The Control Room Operator shall hold a reactor operator license. CALVERT CLIFFS - UNIT 2 6-la Ame rGment Nc' EE/97/JJ2/JJ/,141 _____--_1_____-______-_____-______-___

i ADMINISTRATIVE CONTROLS l 6.3 FAtlllTY STAFF OVAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum ll - qualifications 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 i 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-i Nuclear Training and shall meet or exceed the requirements and i recommendations of Section 5.5 of ANSI-N18.1-1971 and Appendix "A" of j 10 CFR Part 55, as applicable, i 6.4.2 A training program for the Fire Brigade shall be maintained under l the direction of the General Supervisor-Planning and Support and shall meet or exceed the reouirements of Section 27 of the NFPA Code-1975. l 6.5 REVIEW AND AUDil f -6.5.1 PLANT OPERAT1QNS AND SAFETY REVIEW COMMITTEE (POSRC) FUNCTION l t

6. 5.' l.1 The POSRC shall function to advise the Plant General Manager on l

l all matters related to_ nuclear safety. j 1 COMPOSITION 6.5.1.2 The POSRC shall' be composed of at least seven, but no more than ten, members,-including the Chairman-Members shall collectively have . experience-in the following areas:

Nuclear Operations-Electrical and Controls Maintenance Chemistry Mechanical Maintenance-Nuclear Engineering i

Radiation Safety' Plant Engineering Design Engineering Members shall be appointed in writing by the Plant General Manager. Members _ shal1~ have a minimum of eight years power plant experience of l which a minimum of three years shall be nuclear power experience. At least-one member shall have an SR0 license on Calvert Cliffs Units 1 and 2-i CALVERT CLIFFS - UNIT 2 6-6 Amendment No. JJ/25/JE////EE/ S}/JJZ,141 9 er - ww e = +s -w r r

ADMINISTRATIVE CONTROLS t CHAIRMAN 6.5.1.3 The Chairman and alternate Chairmen of the POSRC shall be appointed in writing by the Plant General Manager. Chairmen shall have a minimum of 10 years power plant experience of which a minimum of three years shall be nuclear power experience. ALTERNAT.Eji 6.5.1.4 All alternate members shall be appointed in writty by the Plant General Manager. Alternate members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience. i MEETING FRE0VENCY 6.5.1.5 The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or one of the designated alternates. [ OV0 RUM 6.5.1.6 A quorum of the POSRC shall include the Chairman or one of the designated alternate chairmen and shall consist of a majority of the members, including alternates. No more than half of the quorum shall be alternates, including an alternate chairman. RESPONSlQ1LITIES 6.5.1.7 The POSRC shall be responsible for the following except for those items designated for review by the Prncedure Review Committee or i Qualified Reviewer in accordance with Specification 6.5.2 and 6.5.3, respectively: a. Review of 1) all procedures required by Specifi;ation 3 and changes thereto, and 2) any other proposed procedure changes thereto as determined by the Plant Ge.wral l.iager to affect nuclear safety. Cross-disciplinary reviews of these procedures are conducted in r accordance with administrative procedures in addition to the reviews conducted by POSRC, the Procedure Review Committee, or Qualified Reviewer. b. Review of all proposed tests and experime ts that affect nuclear safety. c. Review of all proposed changes to Appendix "A" Technical Specifications, d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. CALVERT CLIFFS - UNIT 2 6-7 Amendment No. JJ/JE/2E/7E/EE/ EJ/JJ/,141 L a

_ _ _. _. -. _ _ _ _. _ - _ ~.. _ _. _ l =! t L ADMINISTRATIVE CONIRQLS j .= e, - Review of the Plant Security Plan'and implementing procedure's l and shall submit recommended changes to tho Off-Site Safety i -Review Committee. -[ f.- Review of the Emergency Plan and ..plementing procedures and l shall submit recommended changes to the Off Site Safety Review i Committee. t g. Review of changes to the PROCESS CONTROL PROGRAM and the l l OFFSITE DOSE CALCULATION MANUAL. I h.- Review of all 10 CFR 50.59 Safety Evaluations that support i procedures in 6.5.1.7.a and changes or ac ~ :ations in 6.5.1.7.d. j 1. Investigation of all violations of the Technical Specifications - l including the preparation and forwarding of reports covering i evaluation and recommendations: to prevent recurrence to the Plant General Manager, the Vice President Nuclear Energy and to l 1 -the Chairman of the Off Site Safety Review Committee. j. Review of all' REPORTABLE EVENTS. l l l -k. Review of facility operations to detect potential safety -l l hazards. l '. Review of any accidental, unplanned or uncontrolled radioactive l~ -l 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, recommendations and disposition of the corrective action to prevent recurrence and for forwarding-of these reports to the Plant General Manager and the Off-Site l ~ Safety Review Committee. t m. Performence of special reviews, investigations or analyses and: l reports thereon as requested by thel Chairman of the Off-Site Safety Review Committee. i i i i i i I CALVERT CLIFFS - UNIT 2 6-7a Amendment No. JJ/JE/J$/75/SE/ 95/III,141 i [ .~ .~a_,,

-; g - i

i

.ADM BISTRATIVE CONTROLS rqr 7 t AUTHORITY 6.5.1.8. The Plant' Operations and Safety Review Committee shall: _

a.

Recommend to' the approval authority approval or disapproval of procedures considered under.6.5.1.7 a. c. y b.- Recommend to the Plant General Manager approval or disapproval j of items considered under 6.5.1.7(b) through-(h) above, j ~ I c. Render determinations in writing with regard to whether or not: each item considered under 6.5.1.7(a) through (h) abo"e constitut4s'an unreviewed safety question. l r d. Evaluate root causes and recommended actions to prever,t.- - .j i recurrence for items-considered under 6.5.1.7(1) through (1_).- e. Provide written notification within 24_ hours to the Vice -l ~ President-Nuclear Energy and the Chairman of the Off-Site-Safety Review Committee of disagreement between the.POSRC and the responsible approval authority in the case o.'- item 6.5.1.7.a or between the POSRC_ and the Plant General Manager; however, the' Plant General Manager shall have' responsibility for resolution of such disagreements pursuant to 6.1.1 above. e c. -RECORDS j =6.5.1.9 The POSRC shall maintain written minutes of each meeting and l;. copies shall be provided to-the Vice President-Nuclear Energy, Chairman of the Off Site Safety Review Committee, and the Plant _ General Manager, j 6.5.2 PROCEDURE REVIEW COMMITTEE- 't I* FUNCTION-- 6.5.2.1 The Procedure' Review Committee may function to review items listed-in Specification 6.5.1.7(a) in. lieu of_ review by POSRC or i Qualified Reviewer as directed by the Plant General Manager. COMPOSITION. -I.; '6.5.2.2 The Procedure-' Review Committee shall be composed of'a Chairman . and eight _ individuals who shall collectively have expertise in the areas l.- contained in Technical Specification 6.5.1.2 1 t I i m l i i h CALVERT CLIFFS - UNIT 2 6-8 Amendment No. JE##JJJ,141 i L h

m _ _ . ~. _ _ _ _ _ _. - 1 l ADMINISTRATIVE-CONTROLS Members shall be appointed in writing by the Plant General Manager. Members shall have a minimum of eight years power plant experience of which a minimum of'three years shall be nuclear power experience. At least one member shall be a POSRC member or alternate. The charter for the Procedure Review Committee shall-include a description of membership, l qualifications, functions, and reports and shall be described in plant administrative procedures. The Procedure Review Committee may be dissolved at the discretion of the Plant General Manager. i l .GAIRMAN 6.5.2.3 The Chairman and alternate Chairmen of the Procedure Review Committee shall be appointed in writing by the Plant General Manager. -Chairmen shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience. ALTERNATES i 6.5.2.4 All alternate members shall be appointed in writing by.the Plant General Manager. Alternate members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear i power-experience. MEETING FRE0VENCY l 1 6.5.2.5 _The Procedure Review Committee shall meet at least once per calendar month and as convened by the Chairman or his designated - alternates. 0VORUM [ 6.5.2.6 A quorum for the Procedure Review Committee shall consist of the Chairman or one of the designated alternate Chairmen and three primary or alternate members provided at least four disciplines are represented. 1 AUTHORITY l 6.5,2.7 The Procedure Review Committee shall: e a. Recommend to the Approval Authority ap' proval or disapproval of procedures considered under 6.5.1.7(a). b. Render d terminations in writing with regard to whether or not i each procedure under 6.5.1.7(a) constitutes an unreviewed l safety question. c. Provide written notification within 24 hours to the Vice President-Nuclear Energy and the Chairman of the Off-Site Safety Review Committee of disagreements between the Procedure Review Committee and the responsible approval authority. The Plant General Manager shall have responsibility for resolution of.such disagreements pursuant to 6.1.1 above. CALVERT CLIFFS - UNIT 2 6-8a Amendment No. 141 l-i i;

I l ADMINISIRAT1VE CON 1BQLS RfC.0ED.it j 6.5.2.8 The Procedure Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Plant General Manager. i LL3_ QUALIFIED REVIEWLRS l L M "1DB I l S.' J.1 The Plant General Manage.' may designate $Pecific procedures or i cl o ses of procedures described in Specification 6.5.1.7.a to be reviewed t by Qualified Reviewers in lieu of review by POSRC or the Procedure Review l Committee. AUTHORITY 6.5.3.2 Qualified Reviewers shall: i a. Recommend to the approval authority approval Jr disapproval of designated procedures and changes considered under 6.5.1.7.a. i and l b. Render determination in writing with regard to whether or not [ each procedure under 6.5.1.7.a constitutes an unreviewed l safety question. t c. Provide written notification within 24 hours to the Vice President Nuclear Energy an1 the Chairman of the Off Site Safety Review Committee of disagreements between the Qualified l Reviewer and the approval authority. The Plant'Genaral Manager [ shall have responsibility for resolution of such disagreements i' pursuant to 6.1.1. above. t CERTIFICATION 6.5.3.3 Qualified Reviewers shall be nominated, trained, and certified in accordance with adt.iinistrative procedures. Certification shall'be by i a department manager.. l 6.5.3.4 Certification requirements of personnel designated as Qualified i Reviewers shall be in accordance with administrative procedures, j } i ? -ii I CALVERT CLIFFS-- UNIT 2 6-8b Amendment No.141

@!ilNLLMIMl0RIR0LS Qualified Reviewers shall have: a. A Bachelors degree in engineering, related science, or technical discipline, and two years of nuclear power plant experiencet DE l b. Six years of nuclear power plant experience l c. Equivalent combination of education and experience as approved by a Ocpartment Manager. RECORDS l 6.5.3.5 Review of precedures by Qualified Reviewers shall be documented f in accordance with administrative procedures. 6.5.4 Off-Si1E SAFETY R(yJDi COMMITTEE 1055R01 FUNCTICN 6.5.4.1 The Off Site Safety Review Committee shall function to provfde l independent review and audit of designated activities in the areas of: l 1 a, nuclear power plant operations l i b. nuclear engineering ~ c. chemistry and radiochemistry i d. metallurgy and non destructive examination i e. Instrumentation and control f. radioingical safety g. mechanical and electrical engineering i f h. quality assurance practices r i h i i i t { CALVERT CLIFFS UNIT 2 6-8c Amendment No.141

I ADMINISTRAllVE c0ff1ROLS COMPOSITION i 6.5.4.2 The OSSRC shall be composed of at least seven members, including l the Chairman. Pembers of the OSSRC may be from the Nuclear Energy Division or other BG&E organization or from organizations external to BGLE. OVAllFIC ATIO!G 6.5.4.3 The Chairman, members and alternate members of the OSSRC shall l t be appointed in writing by the Vice President-Nuclear Energy and shall have an academic degree in engineering or a physical science, or the equivalent, and in addition shall have a minimum of five years technical experience in one or more areas given in 6.5.4.1. No more than two l. alternates shall participate as voting members in OSSRC activities at any one time. CONSULTANTS 6.5.4.4 Consultants shall be utilized as determined by the OSSRC l -[ Chairman to provide expert advice to the OSSRC. j 1 MEETING FRE0E gl I 6.5.4.5 The OSSRC shall meet at least once per six months. l l OV0 RUM l i 6.5.4.6 The quorum of the OSSRC necessary for the performance of the l 0SSRC review and audit functions of these Technical Specificatlons shall i consist of mo*to than half the OSSRC membership or at least four. members, j whichever is greater. This gaorum shall include the Chairman or his l appointed alternate and the-OSSRC members, including appointed j = lternates, meeting the requirements of Specification 6.5.4.3. No more-l a t than a minority of the quorum shall have line responsibility for operation of the_ plant'.. j ~i 7 i i [ t i CALVERT Cliffs - UNIT 2 6-9 Amendment No. / N U, 141

ADtu!nS1RATIVE CONTROLS i EillDI f 6.5.4.7 The OSSRC shall review: l a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. c. Proposed tests or experiments which involve an unreviewed safety question-as defined in Section 50.59, 10 CFR. d. . Proposed changes in Technical Specifications or this Operating

License, e.

Violation of codes, regulations, orders, Technical Specifications, license ro utrements, or of internal procedures or instructions having nuclear safety significance, f. Significant operating abnormalities or deviations from normal and ev icted performance of plant equipment that affect nuclear safety. g. All REPORTABLE EVENTS. h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components. 1. Reports and meetings minutes of the POSRC. CALVERT CLIFFS - UNIT 2 6 Amendment No. #,141 L

ADMINISTRATIVE CONTROLS AW_Ilit 6.5.4.8.1 Audits of facility activities shall be performed under the l cognizance of the OSSRC. These audits shall encompass: a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b. The performance, training and qualification of the entire facility staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months. d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR Part 50, at least once per 24 months. e. Deleted. f. The Safeguards contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d), g. Any other area of facility operation considered appropriate by the OSSHC or the Vice President Nuclear Energy. h. The facility Fire Protection Program and implementing procedures at least once per 24 months, i. An independent fire protection and loss prevention program inspection and audit shall;be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm. J. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months. k. The radiological environmental monitoring program and the results thereof at least once per 12 months. 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months, The PROCESS CONTROL PROGRAM and implementing procedures for m. processing and packaging of radioactive wastes at least once per 24 months. CALVERT CLIFFS - UNIT 2-6-11 Amendment No. U/#/E5/U,141

ADfi1NISTRATIVE C0!i1EQLS n. The performance of activities required by The Quality Assurance Program for effluent and environmental monitoring at least once per 12 months. 6.5.4.8.2 Review of facility activities shall be performed under the l cognizance of the OSSRC. These reviews shall encompass: a. The facility Emergency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR Part 50.54(t). AUTHORITY 6.5.4.9 The OSSRC shall report ta a'id advise the Vice President Nuclear Energy on those areas of respe $sibil *.y sper' fled in Section 6.5.4.7 and 6.5.4.8. RECORDS 6.5.4.10 Records of OSSRC activitica shall be prepared, approved and l distributed as indicated below: a. Minutes of each OSSRC meeting shall be prepared, a) proved and forwarded to the Vice President-Nuclear Energy wit 11n 14 days following each meeting, b. Reports of reviews encompassed by Section 6.5.4.7 above, shall l be prepared, approved and forwarded to the Vice President-Nuclear Energy within 14 days f-lowing completion of the review. c. Audit reports encompassed by Section 6.5.4.8 above, shall be l forwarded to the Vice President-Nuclear Energy and to the management positions responsible for the areas audited within 30 days after completion of the audit. . 6.6 REPORTABLE EVENT-ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: a. The Commission shall be notified and a report submitted L pursuant to the requirements of Ser. tion 50.73 to 10 CFR Part 50, and b. Each REPORTABLE EVENT shall be reviewed by the POSRC and the results of this review shall be submitted-to the OSSRC and the l Vice President Nuclear Energy. 1 CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 15/EE//J/ES/M,141 w. A

6DtilNISTRATIVE CONTRELS j SAFETY LIMli VIOLATION 6.7 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 r President Nuclear Energy and the OSSRC shall be notified within i 24 hours. I c. A Safety Limit Violation Report shall be prepared. The report i Shall be reviewed by the POSRC. This report shall describe (1) j opplicable circumstances preceding the violation, (2) effects j uf the violation upon facility components, systems or structures, and (3) corrective action taken to prevent i recurrence. I d. The Safety limit Violation Report shall be submitted to the Commission,-tne OSSRC and the Vice President-Nuclear Energy ) within 14-days of the violation. i t { 6.8. PROCEDURES 6.8.1 Written procedures shall be established, implemented and i maintaincd covering the activities referenced below: r a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33,-Revision 2 February 1978. I b. Refueling operation, c. Surveillance and test acti_vities of safety related equipment. L r d. Security Plan implementation. [ e. Emergency Plan implementation. l f. Fire Protection Program implementation.* l f t g. The amount of overtime worked by plant-staff members performing i safety related fu.ations must be limited in accordance with the i NRC Policy Statemer.t on working Hours (Generic Letter No, j .8212). POSRC is only required to review fire Protection procedures and l i l changes thereto which affect nuclear safety, j !l i CALVERT Cliffs UNIT 2. 6 13 Amendment No. JJ/15/JJ/JE/JJ/. [ H/ill,141 t .._.,_.._..__..,_.._._,,._____.__A.. _,__,,_...~_,_._,_.___,,_J

8D!i]HISTRATIVE CONTRO15 h. PROCESS CONTROL PROGRAM implementation. 1. OFFSITE DOSE CALCULA110N MANUAL implementation. 6.8.2 The Plant General Manager may designate specific procedures or classes of procedures in writing to be reviewed by the Procedure Review Committee or by Qualified Reviewers in lieu of review by the POSRC. Review by the Procedure Review Committee shall be in accordance with paragraph 6.5.2. Review by Qualified Reviewers shall be in accordance with paragraph 6.5.3. 6.8.3 Procedures listed in 6.8.1 shall be approved by the Plant General Manager or by cognizant. Panagers, Superintendents, or General Supervisors (or Directors) that report directly to a Manager prior to implementation as specified by administrative requirements. The approval authority for specific procedures or classes of procedures shall be designated in writing by the Plant General Manager and shall be a different individual from the Qualified Reviewer. 6.8.4 Each procedure of 6.8.1 above and changes thereto shall be l reviewed periodically as set forth in administrative procedures. i l I CALVERT CLIFFS - UNIT 2 6-13a Amendment No. IJ/15/)J/)J/EE/ 91/111,141 L 1

4 ADMINISTRATIVE CONTROLS 6.8.5 Temporary changes to procedures of 6.8.1 above may be made l provided: 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. c. The change is documented, reviewed by the POSRC, the Procedure Review Committee, or by a Cualified Reviewer and approved by the designated approval authority within 14 days of impicmentation. 6.9 REPORTING RE0VIREMENTS 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 summary report of plant startup and power escalation testing shall be submitted _following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel sup)1ier, and-(4) modificaticns that may have significantly altered tie nuclear, thermal, or hydraulic performance 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 operating conditions or characteristics obtained during the_ test 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 commitments shall be included in this report. . CALVERT CLIFFS - UNIT 2 6-14 Amendment No. JA/1$/ Q //J/JJ/ Si/111,141 A

i j ALMNISIRAllJfl0KIROL S 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does l not, cover all three events (ite., initial criticality, completion of l startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three i months until all three events have bean completed. ANNUAL REPORTSM 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 i of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality. 6.9.1.5 Reports required on an annual basis shall include: j a. A tabulation on an annual basis of the number of station, [ . utility,-and other personnel (including contractors) receiving i exposures greater than 100 mrem /yr and their associated man rem l exposure according to work and job functions,. u. e.g., reactor t operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance). waste t processing, and refueling. The dose assignment to various duty l functions may be estimates based on pocket dosimeter TLD, er j film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for, in i the aggregate, at least 80% of the total whole body dose-received from external sources shall be assigned to specific major work functions. b.- The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b). c. Documentation of all failures and challenges to the pressurizer f PORVs or safety valves. l l $i ,12 A single submittal may be made for a multiple unit station. The submittal-should combine those sections that are common to all units at the station. 2Z This tabulation supplements the requirements of 10 CFR Part 20.407, i e CALVERT CLIFFS - UNIT 2 6-15 Amendment No. #,50 'f r =j . _. ~.., - _. - - _ _,,.. _

MMINLS11MI1YLIDR1 ROLE 6.10 RECORD RU D[UDJJ 6.10.1 The following records shall be retained for at least 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 EVLNTS. d. Records of surveillanco activities, inspections and calibrations required by these Technical Specifications, e. Records of reactor tests and experiments, f. Records of changes made to-Operating Procedures, g. Records _of radioactive shipments. h. Records of sealed source-and fission detector leak tests and results.- 1. Recordt of annual physical inventory of all scaled source material of record. 6.10.2 The following records shall be retained for the duration of the facility Operating License: a. Records and drawing changes reflecting facility design modifications made to systems and_ equipment described in the final Safety Analysis Report, b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories. c. Records of facility radiation and contamination surveys, i l-o ( l 1 CALVERT-CLIFFS - UNIT 2 6-19 Amendment No. JA,75 L ._.___._,-_._...-.~._,.,-.,..4.._.., .,.. _. ~.... .. _. _, ~., _ -

ADtil#111M11YLC0!11ROLS d. Records of radiation oxposure for all individuals entering radiation control areas, e. Records of gaseous and liquid radioactive material released to the environs. f. Records of transient or operational cycles for those f acility components-identified in Table 5.7.1. g. Records of training and qualification for current members of j the plant staff. h. Records of in service inspections performed pursuant to these 1echnical Specifications. i. Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records. J.- Records of reviews performed for changes made to procedures or equipment-or review, of tests and experiments pursuant to-10 CFR 50.59. k. Records of meetings of the POSRC, the Procedure Review Committee, and the OSSRC. 1. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13. m. Records of'the service lifes of all safety related snubbers including the date at which the service life commences and associated installation and maintenance records. 5 11 RADIATION PROTECTION PROGRAtj . Procedures for personnel radiation protection shall be prepared . consistent with the requirements of-10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20: a, A.high radiation area in which the intensity of radiation-is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thercto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area. CALVERT Cliffs - UNIT 2 6 20 Amendment No. ##95,141 l

MMMISlfM11YLCMTR01 S b. A high radiation 1.rea in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.12.1.a. above, and in addition locked barricades shall be provided to prevent unauthorized entry into such areas and the i keys shall be maintained by the Supervisor. Radiation Control Operations and the Operations Shift Supervisor on duty under i their separate administrative control l 6.13 SYSTEM INTEGRllY j The licensee _shall implement a program to reduce leakage from systems 1 outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. i This program shall include the following: l b 1. Provisions establishing preventive maintenance and periodic l .isual. inspection requirements, and j 2.. t.eak test requirements for each system at a frequency not to j exceed refueling cycle intervals. 6.14 IODINE MON 110 RING [ The licensee shall implement a program

  • which will ensure the capability l

f to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following: 1. Training of personnel, i i 2. Procedures for monitoring, and I i 3. Provisions for maintenance of sampling and analysis equipment. 6.15 POST ACCIDENT SAMPLING The licensee shall establish, implement and maintain a program

  • which r

will ensure the capability to obtain and analyze reactor coolant, i radioactive iodines; and particulates in plant-geseous effluents, and containment atmosphere samples under accident conditions.. The program l shall include the following: I t 1. Training-of personnel, i 2. Procedures for sampling and analysis, and 3. Provisions for maintenance of sampling and analysis equipment. i It is acceptable.if the licensee maintains details of the program in plant operation manuals (e.g., chemistry procedures, training instructions, maintenance procedures, ERPIPs). j 1 t .CALVERT-CLIFFS - UNIT 2 6-21 0/#//J9/2//E9//M//#/U////#, i Am. No. S /U,96-j r . -, _.... _ _ ~,. _ _,.. - w.- . ~. -

l 1 1 @!iDRSTRATIVE CONTRQLS fil6 PR0R SS CONTROL PROGRAM (PCP) 1 6.16.1 The PCP shall be approved by the Commission prior to implementation, j i 6.16.2 Licensee initiated changes to the PCP: 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the p6cted in which the change (s) was made. This submittal shall contain: a. An evaluation supporting the premise that the chango did 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 the Plant General Manager. l 5 17 Offs 11E DOSE CALCULATION MANUAL (ODCM 6.17.1 The ODCM shall be approved by the Commission prior to implementation. 6.17.2 Licensee initiated changes to the ODCM: 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. This submittal shall contain: a. Sufficient information to support the rationale for the change. -Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and 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' I c. Documentation of the fact that the change has been reviewed and found acceptable by the POSRC.- 2.- Shall become effective upon review by the POSRC and approval of the Plant General Manager. l CALVERT Cliffs - UNIT 2 6 22 Amendment No. EE#J/SJ#EHJJ,141}}

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