ML17319B258

Tech Specs Table 3.3-1 Re Condition Setpoint & Tech Specs Table 6.3-6.8.2,facility Staff Qualifications,Administrative Controls & Safety Limit Violations

ML17319B258
Person / Time
Site:	Cook
Issue date:	03/29/1982
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17319B257	List: ML17319B256 ML17319B258
References
NUDOCS 8204060058
Download: ML17319B258 (15)

Text

TABLE 3.3-1 Continued DESIGNATION CONDITION AND SETPOINT FUNCTION P-7 Mith 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels > 11>> of RATED the automatic block of THERMAL POMER or 1 of 2 Turbine reactor trip on: Low Fi.rst Stage Pressure channels flow in more than one

>37 psigo .-' ~

primary coolant loop, reactor coolant pump under-voltage a'nd under-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-8 Mith 2 of 4 Power Range Neutron P-8 prevents or defeats Flux channe1s - 51Ã of'ATED the automatic b'1ock of THERMAL POMER. reactor trip on low coolant flow in a single loop.

, P-10 -Mith 3 of 4 Power range neutron P-10 prevents or defeats flux channels < 9X of RATED the manual bIock of: Power THERMAL POMER. range low setpoint reactor trip. Intermediate range reactor trip, and intermediate range rod stops.

Provides input to, P-T.

O. C. COOK-UNIT 1 3/4 3-9 82040b0058 820329 PDR ADOCK 05000315 P PDR

CHAIRMAII~~ THE BOARD A )IEF EXECUTIVE OFFICER AEPSC 0

IHOIANA 4 tiIICHIGAtl ELECTRIC CO.

.AND OTHER AEP SUBSIDIARIES VICE CH IRMAtl HP INDIAtlA 8 tiIICHIGAH CONSTRUCTION FLECTRIC CptiIPAH Y AEPSC EXECUTIVE VICE PRESIDENT ~

CONSTRUCTION VICE PRESIDENT AHD NEW YORK AHD INDIANA 4 tiIICHIGAt< I l I I t l l l I I t l I 1 l I 1 1 3 i ENGIHEERIHG ELECTRIC CpfiIPAHY AEPSC

.'iIAtlAGER ENGItlEERIHG I l l I 3 3 l I I I 313 I I I I I I I 1 QUALITY DIVISIONS ASSURANCE AEPSC AEPSC PLAilT MAtIAGER PLANT DONALD C. COOK NUCLEAR PLANT QUALITY ASSUR AtlC E SUP ER VISOR APti1INIS i RATIVE 8 TECIIttICAL SUPERVISION T 'HICAL SUP RVISiptl FUIICTIOHAL DIRECTION TEC,".IIICAL LIAISO'I AplilltiISTRATIVE figure 6.2-1 Offsice Organization for "-acilicv Management and echnical SUDDoz'r D.C. COOK UNi. 1 6-2

PLANT MANAGER ADMUIISTRATIVE MAINTENANCE OPERATIONS SUPERVISOR SUPERINTENDENT TECHNICAL SUPERHITENDENT SOL SUPERIITTENDENT CHIEF PROD. SUPV. FIRE SECURITY STAFF STAFF OPERATIONS PROTECTION OA SUPERVISOR SOL COORDINATOR SUPERVISOR SHIF1'ECURITY TRAINING SHIFT COORDINATOR SUPERVISOR SUPERVISOR SOL ASSISTANI'HIF NUCLEAR PL NT COMPUTER PERFORMANCE CONTROL AND PLANT SUPERVISING INSTRUMENT CHEMICAL RADIATION ENVIRONMENTAL 1'UPERVISOR ENGINEERING PROTECTION COORDINATOR SOL SUPERVISOR ENGINEER SUPERVISOR SUPERVISOR SUPERVISOR l.EGEHDT INSTRUMENT UNIT RADIATION PERFORMANCE PERFORMANCE CHEMICAL SOL SENIOR OPERATOR LICENSE SUPERVISOR MAINTENANCE PROTECTION OL OPERATOR LICENSE SOL>> ENGINEER ENGINEER SUPERVISOR SUPERVISOR SUPERVISOR

~ KEY SUPERVISORY PERSOISIEL

<<~ REPOR'TS ADMINISTRATIVELYTO PLANT MANAGER AND TECHNICALLY TO REACTOR AEPSC OA MANAGER OPERATOR sa EffECTIVE 7/I/St- HOLDS RO OL UNTIL THA1'ATE SHIFT TECHNICAL TECHNICIANS

~ ooo - ADMINISTRATIVE ADVISOR TECHNICIANS AUIOLI A R Y EOUIPMENT OPERATOR FIGURE 6.2-2 FACILITY ORGANIZATIONDONALD C. COOK- UNIT No.l

~ . ADNIiVlSTRATIVE CONTRO 6.3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971'or comparable positions, except for (1) the Radiation Protection Supervisor who shall meet or exceed the quali-fications 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.

6.3.2 Until the newly appointed Operations Superintendent obtains a Senior Reactor Operator's License; all of his licensed functions will be performed by a full time assistant who holds a current Senior Reactor Operator's License.

6.4 TRAINING 6.4.1 A retraining and. replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Mi nager and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SA1.'ETY REVIEW CO>iMITTEE (PNSRC)

FUNCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all, matters related to nuclear safety.

D. C. COOK UNIT 1 6-5

0

~ ~

r gtIHISTRATIVE COHTROLS COHPOSITIOH 6.5.1.2 The PHSRC shall be composed of the:

~ ~

~

Chairman: Plant Nanager or designated alternate member: Assistant Plant Managers Member: Operations Superintendent Hember: Technical Supezint endent Member: Haintenance Superintendent Member: Control and Instr'umen4 Supervisor Hember: Nuclear/Computer Engineering Supezvisor Member: Fl.ant Chemical Supervisor h)ember: Performance Supervising Engine r

'ember: .. Plant Radiation Protection Supervisor Member"r Shift Supervisor Member: Environmental Coordinator "ALTERNATES 6.5.1.3 All alternate members shall b appointed in writin by the PHSRC Chairman to serve on a temporary basis; however, no more than .,vo alternates shall participate as voting embers in PNSRC activities at any one time.

~ ~

V HEETIHG FREQUEHCY 6.5.1.4 The PHSRC shall meet at,'east once per ca1endar month and as convened by the PHSRC Chairman or his d signated al ornate.

OUO RUN 6.5.1.5 A quorum of the PHSRC shall consist of the Chairman or his designated alternate and four embers including alternates.

RESPOHSIB ILITIES 6.5.1.6 The PiISRC sha11 he responsible or:

Review of 1) a11 procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by th P1ant Manager to affec nuclear safety.

b. Review of a11 proposed tests and experiments that a=feet nuclear safety.

0 C. COOK - UHIT 1

4 6.7 SAFEST Y LENET VEOLATION 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 STANGSY within ane hour.

1

b. The Safety Limit violation shall be reported to the Commissfon and to the Chairman of the NSDRC. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Yf'olatfon Report shall be prepared, 'he report

'I}

shall be reviewed by the PNSRC. This report shall descrtbe

'applicable. circumstances preceding the violation, (2) effects af the violation upon facility components, systems or structur s, and. (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the

~

Commission, the Chairman of.,the NSDRC, and the Executive Vice

'4President-Construction'nd days of the violatipp.

Hex York Engineering AEPSC within

~ ~

6.8 PROCEDURES 6.8.I Mrf ten procedures shall be eswblished, implemented and main-lined cavering the activfti s referenc d below:

a. Tne applicable procedures recommended in Appendix "A" of Regulatory Cufde 1.33, November, 1972.

b. Refueling operations.

c. Surveillance and .est ac.fvfties of safety r clat d equi pnent.

d. Security Plan implementation.

e. wer ency Plan impl eaentatfan.

Fire Prate tion Program implementation.

l 6.8.2 "=acn procedure and acministratfve policy of 6.8.1 above, and changes thereto, snail be revfe~wed by the PNSRC and approved by h e 'l>>

Plan>><tanager prior ta impl ementatfon and reviewed periodfcall forth in adminis.ra;ive proc dures.

j D. C. COOK - UNET I 6-1 3 Anendment Na. 22

ATTACHMENT NO. 3 TO AEP:NRC:00659 REVISED TECHNICAL SPECIFICATION PAGES FOR D.C. COOK UNIT NO. 2

TABLE 3.3-1 (Continued)

DESIGNATION- CONDITION ANO SETPOINT FUNCTION P-7 ~ With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux Channels > llew of RATED the automatic block of THERMAL POWER or 1 of 2 Pressure reactor trip on: Low Before . The First Stage channels flow in more than one

> 66 psia. primary coolant loop, reactor coolant pump under-voltage and urder-frequency, turbine trip, pressurizer low pressure, and pressurizer high level.

P-8 With 2 of 4 Power Range Neutron P-8 prevents or defeats Flux channels > 51Ã of RATED the automatic block of THERMAL POWER. reactor trip on low coolant flow in a single loop.

P-lo With 3 of 4 Power range neutron P"10 prevents or defeats flux channels < 9.o of RATED the manual block of: Power THEEQL POWER. range low setpoint reacto~

trip, Intermediate range reactor trip, and intermediate range rod stops.

Provides input to P-7.

0. C. COOK - UNIT 2 3/4 3-8

CHAIRtlAt THE BOARD, A HIEF EXECUTIVE OFFICER AEPSC INDIANA4 iYilCHIGAH ELECTRIC CO.

Atl0 OTHER AEP SUSSIDIARIES 0

0 VICE CHAIRMAN ENGINEERIHG At(0 VICE PRESIDENT AHO INDIANA g ig! CH! GAH CONSTRUCTION ELECTRIC COtiIP A tt Y AEPSC EXECUTIVE VICE P RESIDENT ~ COtlSTRU CTION VICE PRESIDENT AHD tlE'N YORK AHD ItlDIANA4 MICHIGAN llllllllllllllll Illc; EHGIHEERING ELECTRIC COMP AtlY AEPSC MANAGER EilGIHE RIH G DIVISIONS IIIIIIIIIIIIIIIIIIIII ~ . LITY ASSURAHCE AEP SC AEPSC PLAiVT i'ilANAGER P LAtl7 DONALD C. COOK tIUCLEAR PLANT gUALIT ( ASSURAHCc SUP ERVISOR ADMINISTRATIVE 4 7 CHHICAL SUPERVISION TE H N I C AL SUP =RV I 5lO'I FUNCTIONAL DIRECTION Tc"""ICAL LIAI~O'I

~' ACX IN! ST RAT! VE Figure 6.2-l Cfzsf.te Organization ror Facility .'!anagernent and:ec'nnical Support D.C. COOK - Ii'.ITT 2 6-2

PLANT h)ANAGKR OPERATIONS " TECHNICAL ADMNISTRATIVK MAINT E NANCE SUPERINTENDENT SUPERVISOR SUPERINTENDENT SUPE'RINTKNDEN'T SOL CHIEF PROD. SUPV. F IRK OA SECURITY STAFF STAFF OPERATIONS PROTECTION SUPERVISOR SUPERVISOR SOL COORDINATOR SHIFT TRAININO SHIFT SECURITY SUPERVISOR COORDINATOR SUPERVISOR SOL N CLEAR PLANT ASSISTANT PERFORMANCE CONTROL AND PLANT RADIATION ENVIRONME'NTAL SHIF T COMPUTER SUPERVISINO INSTRUMENT CHEMICAL ENOINEERIND PROTECTION COORDINATOR SUPERVISOR ENOINEER SUPERVISOR SUPERVISOR SUPERVISOR SOL SUPERVISOR INSTRUMENT RADIATION LKGEHOl UNIT PERFORMANCE PERFORMANCE CHEMICAL PROTECTION SUPERVISOR MAINTEHANCE SUPERVISOR SOL SENIOR OPERATOR UCKNSE ENOINEER ENOINKER SUPERVISOR SUPERVISOR SOL~

OL OPERATOR UCENSK

~ KEY SUPERVISORY PERSOISIKL e~ REPORTS ADMINISTRATIVELYTO PLANT MANAGER AND TECHNICALLY TO REACTOR AEPSC OA MANAGER OPERATOR OL

~ o- EFFECTIVE T/I/SE- HOLDS RO SHIFT TECIVIICIANS UNTIL THAT DATE T EC H RICAL TECHNICIANS

~ ooo - ADMINISTRATIVE ADVISOR AUXILIARY EOUIPMEN'T OPERATOR FIGURE 6.2-2 FACILITY ORGANIZATION DONALD C. COOK-UNIT No.2

l 6.0 ADMINISTRATIVE C OLS 6.3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum quali-fications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Protection Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who snail 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.

6.3.2 Until the newly appointed Operations Superintendent obtains a Senior Reactor Operator's License, all of his licensed functions will be performed by a full time assistant who holds a current Senior Reactor Operator's License.

6.4 TRAINING 6.4.1 A retraining "and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Manager and shall meet- or exceed the requirements of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC) 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of the:

Chairman: Plant Manager or designated alternate Member: Assi'stant Plant Managers-Member: Operations Superintendent Member: Technical Superintendent Member: Maintenance Superintendent Member: Control and Instrument Supervisor Member: Nuclear/Comput'r Engineering Supervisor Member: Plant Chemical Supervisor Member: Performance Supervising Engineer Member: Plant Radiation Protection Supervisor Member: Shift Supervisor Member: Environmental Coordinator D. C. COOK UNIT 2 6-5

AGMINISTRATI YE TROLS 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 STANOBY within one hour.

b. .The. Safety Limit violation shall be reported to the Commission and to the Chairman of the NSDRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The, report shall be reviewed by the PNSRC. 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,Reaort.shall he. submitted to the Coimnissfon, .the.'Chairman of the'SDRC,.and,the Ececutive Vice President&onstruction and New York Engineering AEPSC within l4 days of the violation.

6.8 PROCEOURES 6.8.1 Mritten procedures shall be established, implemented and main-tained covering the activities refer need below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security 'Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

6.8.2 Each proc dure of 6;8.1 above, and changes thereto, shall be reviewed by the PNSRC and approved by the Plant Manage orior zo imole-mentation and reviewed periodically as set forth in adminis rative procedures.

0. C. COCK - UNIT 2 6-13

gI