ML20134B039

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Proposed Tech Spec Changes Eliminating Vice president-supply & Vice president-engineering & Const Positions & Adding Vice president-nuclear Energy
ML20134B039
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 11/01/1985
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20134B032 List:
References
NUDOCS 8511110195
Download: ML20134B039 (26)
v • d • e


Text

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6.0 A0ft!NISTRATIVE ' CONTROLS  :#

6.1 RESPONSIBILITY 6.1.1 ThernanagerJaclear Operations

,al;at grhtendtet shall be responsible for overall facility I operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION ,

OFFSITE, 6.2.1 The offsite organization for facility management ano technical support shall be' as shown on Figure 6.2-1.

FACILITY STAFF S

6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be comoosed of at least the minimum snif t crew composition shown in Taole 5.2-1.
b. At least one licensed Operator snall be in the control room wnen fuel is in the reactor.
c. At least tno licensed Operators shall be pres'ent in tne control room during reactor start-up, scneduled reactor shutdown and during recovery from reactor trips. .

d, An individual qualified in r;diation protection procedures '

shall be on site when fuel is in the reactor.

e. All CORE ALTERATIONS after the initial fuel loading snali ce directly supervised by eitner a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Hancling wna has no other concurrent responsibilities during tnis o pera ti o n.
f. A sita Fire Brigade of at least 5 memoers shall be maintained onsite at all times. The Fire Brigade shall not include tne minimum shif t crew necessary for safe snutdown of botn units (4 memDers) or any personnel required for other essential

' functions during a fire emergency.

CALVERT CL:FFS - U't!T 1 6-1 Amendment tio. 25, 12 8511110195 851101 PDR ADOCK 05000317 P PDR f -

Chairman of the Board I .

President Vice President ,_____________________________. Vice President Vice President i General Services . Nuclear Energy Electric Inter-l connection and

' Operations

  • Corporate .

Responsibility ,

For Fire i Protection l l

Manage' r r----'-- , Manager Manager Manager Manager Manager Real Estate & e---i OSSRC 1 Nuclear Nuclear . Quality Assurance Nuclear Electric Offica Services l '---r___- '___ Operations Engineering Services & Staff Services Maintenance Test l ,

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i i l l I Director r- - - ' - -- ; General Staff Staff Staff Staff Staff Security l POSRC 'eJ Supervisor Services L------ j Operations 7 5

Fire Prevention Unit Assistant General Supervisor Nuclear Security [

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FIGURE 6.2-1 i MANAGEMENT ORGANIZATION CHART CALVERT CLIFFS NUCLEAR POWER PLANT "

BALTIMORE GAS & ELECTRIC COMPANY "

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Vice President Nuclear Energy .

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  • I l Plant Operattuns Manager Manager Manager Manager

%fety Review Nuclear Nuclear Engineering Quality Assurarce and Nuclear Committee Opetastons 5ervices Staff Services Maintenance Nuclear Security l l l 1 I I I I I I GS GS GS GS Gs G5 GS G5 GS Quality G5 Plant & Licensing GS Planning GS GS Quality Control Electrical Operal(ons Radiation Chemistry Control & Design Project and Fuel Quality and Nuclear Mechanical and 5upport and /

Safety Support Engineering Engineering Management Assurance Support Training Maintenance Services Controls i I SRO Procedures l Shiit Development & Maintenance Supervisor Modifications Coordmation Acceptance LEGEND: G5 - ' General 5upervisor f l SRO - Senior Reactor Operator License '-

l SRO .

RO - Reactor Operator License O I

Control Room Supervisor I

RO Control Room Operator l U Plant

  • l Operator FIGURE 6.2-2 l

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l ORGANIZATION CHART (TWO UNIT OPERATION) D l CALVERT CLIFFS NUCLEAR POWER PLANT 1 BALTIMORE GA5 & ELECTRIC COMPANY w

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Adit!NISTRATIVE CONTROLS

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6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparat,le positions, except for 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 - Tr:' ':; :nfLcteur TrMnia)

Teck-ita! Sr" ice: 'er the "uclear 80rer Depart e-t i=d the Eene-il n;;7gi:a7 fa7l t'e "r:&ct ir ti-t::: c: Sp:r* ent pnd shall meet or exceed the requirements and recommendations of Section 5.5 cf 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 Tr:i-ing :nd T::bni::1 Scrsic:: :nd shall meet or exceed the requirenents of Section 27 of the NFPA Code-1975. 0 Qual;fy 6ntr,,)

6.5 REVIEW AND AUDIT

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

FUNCTION 6.5.1.1 manuyer melear Operd ens The POSRC shall function to advise the "?:n E;;r'nt::d:nt on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC shall Se composed of the:

Chairman: "!::t E;;r'nt: d::t 17hnuger:.due! ear Operchns itember: General Supervisor - Operations Member: General Supervisor - Electrical and Controls Member: General Supervisor - Chemistry

"-- h er : "-'nci- 1 Eng h::r "hnt Sgh: ring E h:r Member: Generaf Supervisor - Mai-t:::ne: :nd "-di'i :ti::: /Ilechau scal /fa Mu Member: "

,'nci?:1 EN;in::r In::r: N:I Sn:;=:ntl A .lFua .s pgrviser-licenang Member: General Supervisor - Radiation Safety anynwd Member: General Supervisor Tr:f 'n; : d T::h-i::1 Sr;i:::

Plant ml. Pr<,}ect Engin.<ry 6.5.1.3 All alternate members'shall be appointed in writing by the POSRC Chairman to serve on a temporary basis; however, no more than two alternates l shall participate as voting members in POSRC activities at any one time.

h CALVERT CLIFFS - UNIT 1 6-6 Amendment No. 26, A3, 3), M/ 85

.w. A

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.

l RESPONSIBILITIES 6.5.1.6 The POSRC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as detenmined by the Phrt E : '-t-Wt to affect nuclear safety.

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b. Review of all proposedu-tv%eu Operar.watests and experiments that affect nuclear safety. ,
c. Review of all proposed changes to Appendix "A" Technical Specifications.

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d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety,
e. Investigation of all violations of the Technical Specifications includ-ing the preparation and forwarding of reports covering evaluation and reconsnendations to prevent recurrence to the .".:::;;r ";;h:r Pr::- Wee fhsMen9

} ,g and to the Chairman of the Off Site Safety Review Consnittee.

f. Review ofill REPORTABLE EVENTS.

9 Review of facility operations to detect potential safety hazards,

h. Perfonnance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off Site Safety Review Consmittee.
i. Review of the Plant Security Plan and implementing procedures and shall 4 submit reconsnended changes to the Off Site Safety Review Consnittee.
j. Review of the Emergency Plan and implementing procedures and shall submit reconsnended changes to the Off Site Safety Review Committee.
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, reconsnendations and disposition of the corrective action to prevent .

recurrence and for fonvarding of these reports to the Punt 4 rht:

and the Off Site Safety Review Consnittee. me.nger-tulear eewe es

1. Review of changes to the PROCESS CONTROL PROGRAM and the 0FFSITE DOSE CALCULATION MANUAL.

CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 26,30,43,H 105

ADMINISTRATIVE CONTROLS -

1 AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Comittee shall:

man. -

a. Recomend to the "!ser-ula< operabas_..t L;;r' .t:nd::t- written approval or disapproval of items considered under 6.5.1.6(a) through l j

(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.

Ylee Presiden t-

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the ."an:;;r Nuclear,f:x:r D:p;r=:nt and the Off Site Safety Review En,, Comittee of disagreement between the POSRC and the %e+Ma*'df er-/Yd.,iear L;;r'nt: d:c.t; however, the-Pl::t Sp;r'-t:nd:34shall have j i

Op. d.fresponsibility as for resolution of such disagreements pursuant l l to 6.1.1 above. g g4 op Hcns RECORDS 1

6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the ." ::;:r %:10:r ";;;r Cep;rin:nt :nd4lce Pm:ajd-hdear Eapthairman of the Off Site Safety Review Comittee. '

at 6.5.2 0FF SITE SAFETY REVIEW COPNITTEE (OSSRC)

FUNC* ION 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:

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a. nuclear power plant operations
b. nuclear engineering
c. chemistry and radiochemistry r
d. metallurgy and non-destructive examination
e. instrumentation and control a
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices CALVERT CLIFFS - UNIT 1 6-8 Amendment No.43

-8

--- - - - - - - V

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i ADMINISTRATIVE CONTROLS (J

t COMP 0SITION N[e Si 6.5.2.2 The OSSRC shall be composed of- at least seven membE sJin';luding the Chairman. Members of the OSSRC may be from the L;;!7 Division or other BGAE organization or from orgainizations external to BG&E and shall collectively have expertise in all of the areas of 6.5.2.1.

OUALIFICATIONS g#aelear Energy 6.5.2.3 The Chairman, members and alternate members offthe OSSRC shall be appointed in writing by the Vice President - L;p!; and shall have ,

an academic degree in engineering or a physical science, or the equiva -

lent, and in addition shall have a minimum of five years technical experience in one or more areas given in 6.5.2.1. No more than two alternates shall participate as voting members in OSSRC activities at any one time.

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CONSULTANTS .

6.5.2.4 Consultants shall be utilized as _ determined by the OS'SkC Chairman to provide expert advice to the OSSRC.

MEETING FRE00ENCY

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6.5.2.5 The OSSRC shall meet at least once per six months.

OUORUM 6.5.2.6 The quorum of the OSSRC necessary for the performance of the OSSRC-review and audit functions of these Technical Specifications shall 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 alternal and the OSSRC members, including appointed alternates, meeting the require-

- ments of Specification-6.5.2.3. Nomorethanaminorityofthe, quorum,Qall

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have line responsibility for operation of the-plant.

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CALVERT CLIFFS - UNIT 1 6-9 Amendment No.43 >

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ADMINISTRATIVE CONTROLS AUDITS s 6.5.2.8.1 Audits of facility activities shall be performed under the cog-  ;

nizance of the OSSRC. .These audits shall encompass:

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a. The~conformance of facility operation to provisions contained within i the Technical Specifications and applicable license conditions at least once per 12 months.

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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 l affect nuclear safety at least once per 6 months.

t d. The performance of activities required by the Quality Assurance i

Program to meet the criteria of Appendix "B",10 CFR Part 50, at

)  ; least once per 24 months,

e. Deleted. '

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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 OSSRC or the Vice Presidentt;;1y,lklear fuerg.
h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.
1. An independent fire protection and loss prevention program inspection

+ , and audit shall be performed at least once per.12 months utilizing i;

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 perfomed by a qualified outside fire consultant
at least once per 36 months.

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, - k. ~ The radiological environmental monitoring program and the results i

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 FROGRAM and implementing procedures for proces- 3

' sing and packaging of radioactive wastes at least once per 24 months.

l -n. The performance of activities required by the Quality Assurance h Program for effluent and environmental monitoring at least once per .

12 months.- l i

CALVERT CLIFFS - UNIT 1 6-11 Amendment No. 25, 82, 105

i ADMINISTRATIVE CONTROLS y

6.5.2.8.2 Review of facility activities shall be performed under the 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 klear Eneray 6.5.2.9 The OSSRC shall report to and advise the Vice President-L;;13 on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of OSSRC activities shall be prepared, approved and distributed as indicated below:

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a. Minutes of each OSSRC meeting shall be prepared, approved and fonvarded to the Vice President-L;;1y within 14 days following each meeting. .hlrar Energy
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President-Sepp 4y N icar within 14 days following completion of the review.

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c. Audit reports encompassed by 'ection 6.5.2.8 above, shall be forwarded to the Vice President- and to the management positions responsible for che areas audited within 30 days after completion of the audit.

g Enert3y

.+- 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Comission 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 " ::;;r 5:1::r ":x:r a:;;r Vice Presicient-Haclear Enery. ' mat. '

CALVERT CLIFFS - UNIT 1 6-12 Amendment No. 42, 82, JA,105

ADSINISTRATIVECONTROLS . a' 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 STAND 5Y within one hour,
b. The NRC Operations Center shall be notified by talephone as soon as possible and in all cases within one hour. The M:::;;r 5:h:r Vice Preddent P:a r 2:;:rt ::t and the OSSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Naclear Energy

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

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Comission, the OSSRC and the M:n;;r i:in Pr.: 2:; " :-t within 14 days of the violation. Vice President- Naelear En,rgy

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6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

9 a. The applicable procedures recomended in Appendix "A" of Regt.latory Guide 1.33 Revision 2 February 1978.

b. Refueling operations.
c. Surveillance and test activities of safety related equipment.
d. Security Plan implementation.
e. Emergency Plan implementation,
f. Fire Prote i on 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 Litter No. 82-12).
h. PROCESS CONTROL PROGRAM implementation.
1. OFFSITE DOSE CALCULATION MANUAL implementation.

I 6.8.2 Each procedure and administrative policy of 6.8.1 above and changes l thereto shall be reviewed by the POSRC and approved by the Phat Lperkten rnanuuer-Nueh '

Opekn s 4en&-prior to implementation and reviewed periodically as set forth in administrative procedures.

CALVERT CLIFFS - UNIT 1 6-13 Amendment No. 26,A3,75,82,105 1

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

a. The intent of the originial procedure is not althed.
b. The change is approved by two members of the olant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. i
c. The change is documented, reviewed by the'POSRC and approved by l the Phat L;; Mat: f::t within 14 days of implementation.

(nanager-Nacteur (pera%ns 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 and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in oower level, (3) installatfon of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have signtficantly altered the nuclear, thennal, or hydraulic perfor-mance of the plant.

- 6.9.1.2 The startuo report shall address each of the tests identified in the PSAR 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.

l CALVERT CLIFFS - UNIT 1 6-14 Amendment No. pf, (f,82,9 C ., , ynam-m _ . . - - - 2 _ _ _ . _W

i ADMINISTRATIVE CONTROLS

b. A high radiation area in which tne intensity of radiation is greater than 1000 mrem /hr shall be subject to ne provisions of 6.12.1.a. above, and in addition locked barricades shali be provided to prevent unauthorized entry into such areas and the

. keys shall be maintained by the Supervisor-Radiation Control-Openh*4l and the Operations Shift Supervisor on duty under their separate i administrative control . l 6.13 ENVIRONMENTAL QUALIFICATION l

6.13.1 By no later tha'n June 30, 1982 all safety-related electrical ecuio-i ment in the facility shall be qualified in accorcance aith the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental

. Qualification of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); or NUREG-0586 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1977.

Copies of. tnese documents are attached to Order for Modification of Licenses DPR-53 and DPR-69 dated October 24, 1980.

6.13.2 P.y no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance witn tne 00R Guidelines or NUREG-0583. Thereafter, sucn records should ce f updated and maintained current as equierent is reolsced, furtner tested, or otherwise furtner qualified.

6.la SYSTEM INTEGRITY I

The licensee snail implement a program to reduce leanage from systems sutsice containment tnat would or could: contain hignly radioactive fluics during a

, serious transient or accident.-to as low as practical levels. This aragram lsnall include the following:

1. Provisions establisning preventi've maintenance anc seri0cic l visual inspection requirements, and
2. Leak test requirements far each system at a frequency nnt to exceed refueling cycle interwis.

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,. CALVERT CLIFFS - UNIT 1 6-21 3teet Ja/24 204//r.!/33; il

<J Amendment No. 96 m _

ADMINISTRATIVE CONTROLS i' 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

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 period in which the change (s) was made.

This submittal shall containg

a. An evaluation supporting the premise that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and
b. A reference to the te and the POSRC meeting number in which the change (s) yere reviewed and found acceptable to the POSRC.
2. Shall become effective upon review d!$;YN; i :::;r^!: u ' r-

";;;. 0;F. .r.: ch and approval of P'-. - E;r'..:_ic.t.

the manager helear OperaNons.  %

6.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The ODCM shall be approved by the Commission prior to implementation.

S 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 contains

a. Sufficient information to support the rationale for the change.
p. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a j

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
c. Documentation of the fact that the change has been reviewed and found acceptable by the POSRC.

1

2. Shall become effective upon review by the POSRC and approval of the Mont T -; 2:L 2. lYtanager Mulear Operakiens.

CALVERT CLIFFS UNIT 1 6-23 Amendment No. 105 D

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d(~ 6.0 ACMINISTRATIVE CONTROLS 6.1 RESPONS! Sit'TY Insout 5.1.1 The Oc.;per.lV.h:leur

-we, .. .e0perahoNS

. snail be resconsible for overall facility l

ooeration and shall delegate in wri:ing tne succession to tnis responsi-bility during his absence.

6.2 ORGANIZATION 0FFSITE 6.2.1 The offsite organi:ation for facility management and technical support snall be as shown on Figure 5.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be ecmoosed of at leas :he minimum shift c'rew composition snown in ~1ble 6.2-1.
b. At least one licensed Operator shall be in the controi room when fuel is in the reactor.

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c. At least two licensed Operators snall ::e cresent in the control room during reactor start-uD, schecuted reac or shutdown and during recovery from reactor trips.

d .' An individual qualified in radiation protection oracecures shall be on site when fuel is in the reactor.

e. All CORE ALTERATIONS after :ne initial fuel loacing shall be directly supervised by either a Itcensed Senior Reactor Operator or Senior Reactor Coerator Limited to Fuel Handling wno has no other concurrent resconsibilities during this operation,
f. A site Fire 3rigade of at less: 5 memcers snall be maintained onsite at all times. The Fire Brigace shall not include :ne minimum shift crew necessary 'or sa fe snutdown of both uni s (4 members) or any personnel required for etner essential functions during a fire emergency.

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CALVERT CLIFF 3 - UNIT 2 6-1 Amencment No. I4 5

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Chairman cf the Board I

President I

Vice President , ___.......___....._....___... Vice President Vice President '

General Services . Nuclear Energy Electric Inter- :

l connection anc'

' Operation

' Corporate l Responsibility l For Fire i Protection l l

l Manager e----'-- , Manager Manager Manager Manager Manager Real Estate & r---i OSSRC : Nuclear Nuclear Quality Assurence Nuclear Electric of fica Services l '-r- _ _ _ _ ' _ _Operations

_ Engineering Services & Staff Services Maintenance Test 6

l i i l l l s .

Director r-- '-- ,, General Staff Staff Staff Staff Staff es Security l POSRC ' Jr Supervisor -

j Services L------ a Operations Fire Prevention Unit Assistant General Supervisor Nuclear c4 Security b R

b FIGURE 6.2-1 I v1 MANAGEMENT ORGANIZATION CHART u.

CALVERT CLIFFS NUCLEAR POWER PLANT G BALTIMORE GAS & ELECTRIC COMPANY V W

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T

r Vice President Nuclear Energy "

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I Plant Operations Manager I Safety Review Manager Manager Nuclear Nuclear Engineering Manager Committee Operations Quality Assurance and Services Nuclear Staff Services Maintenance

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Nuclear Security I I I -1 I I f

I I I GS GS I GS GS GS GS GS Quality GS Plant & Licensing GS c5 GS Operations Radiation Chemistry Control & Planning GS GS Quality Control Design Project and Fuel Quality Electrical

    • Safety Support and Nuclear Mechanical and Support Engineering Engineering Management Assurance Support and Training Maintenance Services Controls i I SRO Procedures Shift Development & Maintenance Supervisor Modifications Acceptance Coordination r.)f i LEGEND: GS - General Supervisor 4l SRO SRO - Senior Reactor Operator License Control Roorn RO - Reactor Operator License Supervisor ,

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r RO Control Room >

Operator l r4 1 Plant Operator I-FIGURE 6.2 2 2 ORGANIZATION CHART (TWO UNIT OPERATIONI I CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE GAS & ELECTRIC COMPANY

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- . .. - . _ = . - -

1 ADMINISTRATIVE CONTROLS

. D' 6.3 FACILITY STAFF QUALIFICATIONS l 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for 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 na' alysis of the plant for transients and accidents.

, 6.4 TRAINING t

6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Tr;ini;; .;d MudeAt Traw

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g it. Tc;f;:th: .". ' := = h;:rr::t and shall meet or exceed the requirements "'-- -fr- l and recosmiendations 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 - Tni ' ; ::d int. in 0.csice-j meet or exceed the requirements of Section 27 of the NFPA Code-1975. ad t hand sh 6.5 REVIEW AND AUDIT @ '

h 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

FUNCTION

/%uagenkelear Opera!**NS

6. 5.1.1 The POSRC shall function to advise the "h:2 L ar' t;;fn ; on all matters related to nuclear safety.

i COMPOSITION 6.5.1.2 The POSRC shall be composed of the:

Chairman: "h:t hpr' trf=t Samger Oclev O ra.fm>.s $

Member: Ger.eral Supervisor - Operations i

Manber: General Supervisor - Electrical and Controls Member: General Supervisor - Chemistry

".-t:r; " ' ='; ? 5:; inn: "h :t 5;; h nri;; .".chei Hanber: General Supervisor .":St:=== ;;d .".edi fice tte.m O;gcjg,,,f $ w revauc i

Member:

Member:

" '=ig! E ;ir::: - I : r: "=? " r;- :;06ee'8 N/e"'50AM"5'i General Supervisor - Radiation Safety F^d fuel / Moue 3eever.

Member: General Supervisor - Tn'-' ; rd T: 5-in! Er"ic :

ALTERNATES Plaut a.mL Project ENyueenWg 6.5.1.3 Ali alternate manbers shall be appointed in writing by the POSRC Chairman to serve on a temporary basts; however, no more than two alternates shall participate as voting members in POSRC activities at any one time.

CALVERT CLIFFS - UNIT 2 6-6 Amendment No. 77, ?$. 36, (A/,68*

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ADMINISTRATIVE CONTROLS METING FREQUENCY 6.5.1.4 The POSRC shall meet at least once per calendar month ank as convened by the FOSRC Chaiman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the POSRC shall consist of the Chaiman or his designated alternate and four members including alternates.

RESPONSIBILITIES-6.5.1.5 The POSRC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes thereto. 2) any other proposed procedures or changes thereto as c t

b. detemined by the e ".'m:.0 '9:$^rtCre.2rwust pr.ivvaea r to affect nuclear safety. -

Review of all proposed tests and experiments that affect nuclear g safety.  ;

c. t Review of all proposed changes to Appendix "A" Technical Specifications, d.

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Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifications includ-ing the preparation and forwarding of reports covering evaluation and ,

D gq_g recommendations to prevent recurrence to the %;r - i:t=r "r:r/*3 Oe54#r-

_2 and to the Chairman of the Off Site Safety Review Committee.

f.

Review of all REPORTA8LE, EVENTS.

g.

Review of facility operations to detect potential safety hazards, h.

Perfomance of special reviews, investigations or analyses and reports j thereon as requested by the Chairman of the Off Site Safety Review Committe..

,. 1

-- Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off Site Safety Review Coeurittee.

j .

Review of the Emergency Plan and implementing procedures and shall ,

submit recommended changes to the Off Site Safety Review Cesarittee.

k.

Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 255 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

1. g gnd the Off Site Safety Review Committee. #'M*1 * recurrence a Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MNUAL.

CALVERT CLIFFS - UNIT 2 6-7 Amendment No.17.J5,25.75. 86 9 l l

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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Operations and Safety Review Comittee.shall:

, /nanager-hclear OperdooNS

a. Recomend to the A4 ant rkte:L a, written approval or disap-proval of items considered under 6.5.1.6(a) through (d) above. l
b. Render determinittions 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.

\/.ce Pres.deM-

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the F.:n:; r Nuclear ",0;;r Dep:r*c::t and the Off Site Safety Review domittee of disagreement between the POSRC and the M*Mihamper-h/mg Fue9 e ann: n;;r -ted-*dall have  ;

ogra/gt;;c'::::dra; f'a5 6.1.1 above. however, +.he responsibility for resolutinn of such disagreements pursuant t6 *

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g RECORDS -

'"#'Nek Opdra). nogs 6.5.1.8 The POSRC shall maintain written minutes of each meeting and copies shall be provided to the F:n ::r "ed ==- % c- "-^^ ~ t V,ce [(esicfed-f % !ev fue<fg i and Chainnan of the Cff Site Safety Review Comittee.

6.5.2 0FF SITE SAFETY REVIEW C0MMITTEE (OSSRC)

FUNCTION 6.5.2.1 The Off Site Safety Review Consnittee shall function to y provide independent review and audit of designated activities in the

- areas of:

a. nuclear power plant operations -
b. nuclear engineering
c. ,

chemistry and radiochcmistry

d. metallurgy F.nd non-destructive e.xamination l
e. instrianentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices CALVERT CLIFFS - UNIT 2 6-8 Amendment No.26 L:-.- D

] ADMINISTRATIVE CONTROLS COMP 0 SIT 10N AjucJeu [perg 6.5.2.2 The OSSRC shall be composed of at least seven membe , including the Chairman. Members of.the OSSRC may be from the Division or other BG&E organization or from organizations external to BG5E.

QUALIFICATIONS Afstfear INe/gg 6.5.2.3 The Chairman, members and alternate members of the OSSRC shall be appointed in writing by the Vice President - L:;!f 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 6.5.2.1. No more than two alternates shall participate as voting members in OSSRC activities at any one time.

O- -

. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the OSSRC

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Chainnan to previde expert advice to the OSSRC.

MEETING FREOUENCY 6.5.2.5 The OSSRC shall meet at least once per six months.

QUORUM ,

6.5.2.6 The' quorum of the OSSRC necessary for the performance of the OSSRC review and audit functions of these Technical Specifications shall 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 alternate and the OSSRC members, including appointed alternates, meeting the requirements of Specification 6.5.2.3. No more than a minority

- ]f -

of .the quorum shall have line responsibility .for. operation of the plant.

CALVERT CLIFFS - UNIT 2 6-9 Amendment No. 26

h ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8.1 Audits of facility activities shall be perfomed under the cog-nizance of the OSSRC. These audits shall encompass:

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a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

The performance, training and qualification of the entire facility

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b.

staff at least once per 12 months.

c. The .results of actions taken to correct deficiencies occurring in facility equipment, structures, systmas 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 OSSRC or the Vice Presidentt;;!y.Alcreae Entvg
h. The Facility Fire Protectica Program and implementing procedures at
  • least once per 24 months.
1. An independent fire protection and loss prevention program inspection y- 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 1 at least once per 36 months. '
k. The radiological environmental monitoring program and the results i 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 proces-i sing and packaging of radioactive wastes at least once pei 24 months.
n. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per D 12 months.

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CALVERT CLIFFS - UNIT 2 6-11 Amendment No. JJ,3),.86 l

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ADMINISTRATIVE CONTR0t.S 6.5.2.8.2 Review of facility activities shall be perfomed under the ,

cognizance of the OSSRC. These reviews shall encompass: l

a. The Facility Emergency Plan and im'plementing procedures at least l once per 12 months in accordance with 10 CFR Part 50.54(t).

AUTHORITY

-kI& IGM' enc&

6.5.2.9 The OSSRC shall report to'and advise the Vice President !::;iy on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS

~6.5.2.10 Records of OSSAC activities shall be prepared, approved and distributed as indicated below: ,

e

a. Minutes of each OSSRC meeting shall be prepared, approved and fomarded to the Vice President -? ;;!y within 14 days following
  • each meeting. -livaeu Energg
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and fomarded to the Vice President &;;lfA/4/ee ENe/g within 14 days following completion of the review. g
c. Audit reports encompassed by Section 6.5.2.8 above shall be fomarded to the Vice President-!:: !y and to the management positions responsible for the areas 6 audited within 30 days after .

completion of the audit. 1

-A)uclear- Epergg

y. 6.6 REPORTA8LE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE 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 REPORTA8LE EYENT shall be reviewed by the POSRC and the results of this review shall be submitted to the OSSRC and _

the ." :: p: t;?::r " ::: %:. :2. 'jo. fresdens r2 Alve lear bnwyg ,

CALVERT CLIFFS - UNIT 2 6-12 Amendment No. 26,55.75. 86 I

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V g ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION

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6.7.1 The following actions shall be taken in the event a Safety Limit is I violated:

a. The facility shall be placed in at least HOT STAN08Y withiin one hour,
b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The .";;;;r "" M- t/.ce [/e5<ded-7e ;r %g. Z;t and the 055RC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Nwev Ew9sy

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.

h

d. The Safety Limit Violation Report shall be submitted to the i Comunission, the OSSRC and the ";;;g. - L;'eer F; r in. ^-,at dte fres deaf-Eder < within 14 days of the violation.

b ei n 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained g covering the activities referenced below: .

a. The appitcable procedures recommended in Appendix "A" of Regulatory Guide 1.33. Revision 2. February 1978.
b. Refueling operations.
c. Surveillance and test activities of safety related equipment.

v- d. Security Plan implementation.

e. Emergency Plan implementation. '
f. Fire Protection Program implementation.
g. The amount of overtime worked by plant staff manbers performing safety related functfons must be Ifmited 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 C,w eee =deasthereto priorshall be reviewed to imp by the 1.ementation and POSRC reviewedand approved periodically as by setthe "t;;inL;;;'-ter /bingdr-Mudea forth administrative procedures.

D CALVERT CLIFFS - UNIT 2 6-13 .

Amendment No.JJ.28.55.85.36 i

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ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

. a. The intent of the originial procedure is not altered. ,

b. The change is approved by two members of the plant management staff, at least one of whom holds s Senior Reactor Operator's License on the unit affected.
c. The change is documented, reviewed by the POSRC and acoroved by the ."i;;;; L;;;,tt; txt within 14 days of implementation.

$%er-ll0 clear Opr.thuqS 6.9 REPORTING REQUIREMENTS .

ROUTINE rep 0RTS 6.9.1 In addition to the applicable reporting requirements of Title 10, 0 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 ano power escalation testin shall be submitted following (1) receipt of an operating license. (2) g h

amendment to the license involving a planned increase in power level.

(3) insta?lation 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, thenna1, or hydraulic perfor-mance of the plant.

y- 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 r,omparison 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 ta this report. ,

1 CALVERT CLIFFS - UNIT 2 6-14 Amendment No./[ ff. U,75 e

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O ADMINISTRATIVE CONTROLS

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 provided to prevent unauthorized entry into such areas and the keys shall be maintained by the Supervisor-Radiation Control-Oper ahos and the Operations Shift Supervisor on duty under their separate administrative control. .

6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30, 1982 all safety-related electrical ecuip-ment.in the facility shall be qualified in accordance with the provisions of:

Division of Operating React' ors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); or MUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Eguipment", December 1979.

Copies of these documents are attached to Order for Modification of Licenses -

OPR-53 and DPR-69 dated October 24, 1980.'

6.13.2 By no later than December 1,1980, comolete and auditable records must be available and maintained at a central location whicn describe the environmental qualification method used for all . safety-related electrical equipment in suf"cient detail to document the degree of comoliance with the 00R Guidelines or MUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.

6.14 SYSTEM INTEGRITY -

The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain hignly raoicactive fluids during a serious transient or accident to as Icw as practical levels.

This program snali include t'te following: ,

1. Provisions establishing preventive maintenance and ceriodic visual inspection requirements, and
2. Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

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l CALVERT CLIFFS - UNIT 2 6-21 9tddt/Ja/2f/894 Amendment 33, 77 i .

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i . 8 ADMINISTRATIVE CONTROLS O 6.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Commission prior to implementation.

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 period in which the change (s) was made.

This submittal shall contains

a. An evaluation supporting the pre nise that the change 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 PO5RC meeting number in which the c change (s) were reviewed and found acceptable to the PO5RC. - -
2. hw tre POS8c. Q i Sha!!

become effective upon review _ _ ,

. _ , _ _ - :; :-- ^ * ' - " ' - _ - t

- --. E ;- . _.; rl; and approval of .*- : E;:ic : f a t

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-rne 97 wager-Nuclect O rahe":

I 6.17 OPP 5ITE DOSE CALCULATION MANUAL (ODCM) f 4

6.11.1 The ODCM shall be approved by the Commission prior to implementation.

g 6.17.2 Licensee initiated changes to the ODCM:

1.

Shall be submitted to the Commission in the Semiannual Radioactive Fffherit Release Report for the period in which the diange(s) was made i

effective. This submittal shall contains

a. Sufficient Information to support the rationale for the change.

Information submitted should consist of a package of those pages of the

y. 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
c. Documentation of the fact that the change has been reviewed and found wpMie by the PO5RC.

2.

Shall become effective upon review by the PO5RC and approvy of the Plane-L; L' .2 4-^L lhwager.f)w. lear OfeM oNS i

CALVERT CLIFFS UNIT 2 6-23 Amendment No. 86

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