ML20236B120

Proposed Tech Specs Changes Consisting of Administrative Corrections

ML20236B120
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/22/1987
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20236B107	List: ML20236B105 ML20236B120 ML20236B322
References
NUDOCS 8707280349
Download: ML20236B120 (30)

Text

A I h

ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES July 22, 1987 l

8707280349 070723 PDR ADOCK 05000155 P PDR '

,s Pages I

I TSB0387-0015-NLO4  !

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E , .

CONTENTS ~(Contd) 8.0 kesearch and Development Program (Deleted) . .. . . . . . 79 -

91 9.0 Inservice Inspection and Testing . . . . . . . . . . . . . 92 - 102 9.1 Applicability . . . .. . . . . . . . . . . . . . 92 9.2 Objective . . . . . . . . . . . . . . . . . .. . . . 92 9.3 Specifications . . . .. . . . . . . . .. . . . . . 92 9.4 Basis . . . . . . . . . . . . . . . . . . . . . . . . 92 10.0 (Section 6.0) Administrative Controls . . . . . . . . . . . 103 + 129 l 6.1 Responsibility . . . . . . . . . . . . . . . . . . . 103 6.2 Organization . . . . . . . . . . ._. ... . . .. . 103 - 106 6.3 Plant Staff Qualifications .. . . . . . . . . . . . 107 6.4 Training . . . . . . . . . .. . . . . . . . . . . . 107 6.5 Review and Audit . . . . . . . . . . . ... . . . . 107 - 113 6.6 Deleted . . . . . r . .. . . . . . . . .. . . . . . 13 3 G.7 Safety Limit Violation . . . . . . . . . .. . . . . 113 6.8 Procedures . . . . . . . . .. . . . . . . . . . . . 113 - 114 6.9 Reporting Requirements . . . . . . . . .. . . . . . 114 - 120 6.10 Record Retention . . . . . . . . . . . . . . . . . . 120 - 122 i 6.11 Radiation Protection Program . . . . . . . . . . .. 122 6.12 High Radiation Area . . . . . . . . . .. . . . . . 123 - 123a 6.13 (Deleted) . . . . . . . . . . . . . . .i . . . . . . 124 l 6.14 Prosc66 Control Program . . . . . . . . . . . . . . . 125 6.15 Offsito Lose Calculation Manual (ODCM) . . . . . . . 125 6.16 Radioactive Materiale Sources . . . . . . . . . . .. 126 - 129 l

11.0 (Section 3.1.4/4.1.4) E6ergency Core Cooling System . . . . 130 - 135 (Section 3.1,5/4.1.5) Reactor Depressurizatien System . . . 136 - 142 (Section 3.3.4/4.3.4) Containment Spray System . . . . . . 143 - 145 (Section 3.5.3/4.5.3) Emergency Power Sources . . . . . .. 146 - 149 12.0 Fire Protection Program .. . . . . . . . . . . . . . . . 150 - 157 (Section 3.3.3.8/4.3.3.8) Fire Detection Instrumentation . 150 - 151 (Section 3.7.11.1/4.7.11.1) Fire Suppression Water System . 152 - 153 (Section 3.7.11.2/4.7.11.2) Fire Spray / Sprinkler Systems . 154 (Section 3.7.11.5/4.7.11.5) Fire Hose Stations . . . . . . 155 (Section 3.7.12/4.7.12) Penetration Fire Bartiers . . . . . 156 - 157 13.0 Radiological Effluent Technical Specifications . . . . . . 158 - 186 13.1 Radiological Eff].uent Releases . . . . . . . .. . . 158 - 173 13.2 Radiological Environmental Monitoring . . . . . . . . 174 - 186 11 Proposed TSB9387-0015-NLO4

t 2

1.2 DEFINITIONS Various provisions of these Technical Specifications set forth

' limitations and restrictions which depend upon modes of operation.

The following modes of operations (1.2.1 through 1.2.6) are defined to clarify.the intent of such provisions,-and are not the same as, nor should they be confused with, the positions of the mode selector switch described in Section 6.1.3.

1.2.1 POWER OPERATION - is any operation other than SHUTDOWN or COLD SHUTDOWN with the reactor vessel closure bolted in place.

1.2.2 CORE ALTERATION - is any completed planned sequence of movements l of core components resulting in either a net change in the configuration of the reactor core or a net gain in core reactivity.

1.2.3- REFUELING OFERATION - is any operation with any of the reactor vessel closures open during which a CORE ALTERATION, or other operation which might increase core reactivity, is in progress.

1.2.4 MAJOR _ REFUELING - is any REFUELING OPERATION with the head off l during which four or more fuel bundles are added, exchanged or repositioned in the reactor core.

1.2.5 SHUTDOWN - is any reactor condition meeting the following l requirements:

(a) All or all but one of the control rods are fully inserted in the reactor core; and (b) Primary system coolant water temperature is less than 212'F.

1.2.6 COLD SHUTDOWN .is a reactor condition involving no fuel in the l core, or a reactor condition meeting with the following requirements.

(a) All of the control rods art. fully inserted in the core and withdrawal pt2 vented by means of the keylock re36ctor switch, the key to which is in the possession of the Shift Supervisor; and j (b) The reactor coolant syster is at atmospheric pressure.

(c). (DELETED) 1.2.7 DOSE EQUIVALENT I-131 - Is that concentration of I-131 microcuries ,

per milliliter, which alone would prodgce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and r 1-135 actually presen+. The thyroid dose conversion factors used )

for this calculation saall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

Proposed TSB0387-0015-NLO4

17 4.1.2 (Contd)

L Minimum Time to Put System 30 in Full Operation Following Signal,-Seconds Core Spcay System:

Type Sparger Ring With Spray Nozzle Capacity of Sprays, Gpm 400 Nozzle Pressure, Psia 115 Backup Core Spray System:

Type Sparger Nozzle Centered Over Core Capacity of Sparger, Gpm 470 Nozzle Pressure, Psia 115 Core Spray System Recirculation:

Number Pumps 2 Number Heat Exchanger 1 6

Heat Removal Capacity, Btu /h 8 x 10

@'28.4*r Log Mean Temperature Difference (b) Operating Requirements A minimum of one reactor recirculating loop shall be used during all reactor POWER OPERATIONS (ie, recirculating pump suction valve and l 20" discharge valve shall remain open and pump shall be running).

The maximum operating pressure and temperature shall be the same as the reactor vessel. The controlled rate of change or temperature in j the reactor vessel shall be limited to 100*F per hour. All other l

components in the system shall be capable of following this tempera-ture change rate. The safety relief valves shall ba set appropri-ately for all planned reactor operating pressures so that the allowable pressure of 1870 psia (1700 plus 10%) in tLe nuclear steam supply system is not exceeded, At least three (3) steam drum safety valve position monitors shall be OPERABLE during POWElt OPERATION. l Also, one of every two (2) adjacent monitors oriented it. each north-south plane shall be OPERABLE. In the event that any oi these monitoring channels become inoperable, they shall be made OPERABLE prior to startup following the next COLD SHUTDOWN. The energency condeusar shall be OPERABLE and ready for service at all tices during POWER OPERATION. However, should one emergency condeneer tube bundle develop a leak during POWER OPERATION 3 it will be permissible to isolate the leaking tube bundle until the next outage. Both bundles of the emergency condenser shall be available for service during cold to hot p? ant heatup for power production.

If both. emergency cradereser loops become inoperable the plant shall be brought to SUUIDOWN cond4. tion within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to COLD SHUTDOWN condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The shutdown cooling system shall be ready for service during POWER OPERATIONS with the 480 volt circuit breakers for isolation valves M0-7056, MO-7057, M0-7058, and MO-7059 checked "open" when reactor pressure Proposed TSB0387-0015-NLO4

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, / f4.122 (Contd) is above 300-psig.- The.shutdowncooling'systemshallbe;;0PERABLE

-and ready for service during REFUELING OPERATIONS:and the' breakers' for MO-7070 and M0-7071 shall be tagged."open". The primary coolant shall be bampled and analyzed. daily..during. periods,.of POWER.

' OPERATION.- The following are absolute" limits which if' exceeded-shall necessitate reactor SHUTDOWN. Corrective action will necessarily:be taken:at more stringent limits to minimize'the

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/ possibility. 'of :these ~ absolute limits ever being reached.

Conductivity-(Micromho/cm).

Maximum ..

5

' Maximum Transient

• 10

-pH (Lower and Upper L). -4.0 and 10.0-Chloride. Ion (Ppm) 1.0

.Buron- (Ppm)'- 100 Isotopic analysis of the primary coo!. ant to determine the DOSE EQUIVALENT'I-131 concentration shall be' performed at least every.

72' hours'during periods:of operation.

1.;.If'the DOSE EQUIVALENT I-131 concentration exceeds 0.'2 pC1/ml

and is less than or equal to 4.0 pCi/m1,, isotopic an'alysis to-determine DOSE EQUIVALENT I-131 shall be performed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the activity is less than'0.2 pC1/m1'.

2. If the DOSE EQUIVALENT I-131 exceeds 4.0 pC1/m1, the plant shall'be placed in a SHUTDOWN condition'with the main steam isolation valve cloced within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(c): Leakage Limits

1. If the primary coolent system leakage exceeds 1 gpm and the source of leakage is not identified ~ ,the- reas: tor shall be placed in the hot shutdown condition within 12: hours, and cooldown to a COLD SHUTDOWN condition shall be initiated l-within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

-2. If leakage from the primary coolant system exceeds 10 gpm, the l reactor shall be placed in the hot shutdown condition within

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and cooldown to a COLD SHUTDOWN condition shall be l

initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.(DELETED)

,,

• Conductivity is expected to increase temporarily after startupe from cold shutdown. The maximum transient value here stated is the maximum permissible

,and applies only to the period subsequent to a cold shutdown between criticality and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching 20% rated power.

Proposed TSB0387-0015-NLO4

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61 6.4.1 (Contd)

(e) In-Plant Radio-Iodine Measurements Under Accident Conditions Procedures for determining airborne radio-iodine concentrations in occupied areas shall be implemented and technicians shall be trained on an annual basis. Maintenance of the sampling equipment shall occur at least semi-annually and maintenance of the analytical equipment shall occur at least monthly.

6.4.2 Area Monitoring System (a) Fixed' gamma monitors employing scintiJ'ation type detectors shall be installed as follows: (1) two on the refueling deck and (2) one in the control room. Each monitor shall have the following:

(i) A range consistent with expected radiation le.vels in the area to be monitored. (0.01 mR to 10 mR or 0.1 mR to 100 mR or 1 mR to 1,000 mR.)

(ii) An output indicated and recorded in the control room.

(iii) An adjustable high radiation alarm which shall be annunciated in the control room.

The area monitors described above shall normally be in operation; however, individual monitors may be taken out of service for maintenance and repairs. Adequate spare parts shall be on hand to allow necessary repairs to be made promptly.

During monitor outages temporary monitoring shall be provided.

Calibration of monitors shall be performed at least monthly.

Alarm trip points shall be set at a radiation level approximately twice the normal maximum indicated radiation level, but normally not less than one decade above the lowest scale reading.

(b) The two area monitors located on the refueling deck shall provide gamma monitoring of the fuel storage areas and refueling operations. Local alarms shall be provided for these monitors, and alarm setting chall be in accordance with the provisions of 10 CFR 70. In the event that both of these monitors become inoperable during POWER OPERATION or fuel handling activities, l the containment ventilation isolation valves shall be closed.

However, notwithstanding the requirements of 10CFR70.24(a)(2), ,

alarm settings may be raised above 20 mR/br as long as the j overall detection criterion in 10CFR70.24(a)(2) is satisfied and the requirements specified in paragraph 6.4.2(a) above are met.

Proposed ,

)

i i

TSB0387-0015-NLO4

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R

. rt: !T E g 71

- 7.2.4 (Contd) . i I

(c) .TechnicaliSpecialists.On-Site: l 1

(1) The General Electric Company shall have a physicist familiar with the Big. Rock Point Plant present at.the j facility for each initial ~ start-up following refueling. He i shall.he present during-the initial approach to criticality

!e and.shall remain.until at least 10% of rated power.isl i

. reached.  !

1 (2)1 Consumers' Power Company shall_have a Reactor Engineer or his designated alternate who shallibe a licensed senior operator in the control ecmm for all start-ups, special tests or:significant power changes.  ;

7.3- NORMAL'0PERATION  !

7.3.1 General Detailed operating procedures for each. normal mede of plant operation shall be' prepared prior"to operation.

The following is an outline of the principal normal operating procedures having a potential effect on the safe operation of the plant.

7.3.2c Cold Start-Up After Extended Shutdown A cold. start-up shall occur each time the reactor is returned to

. service following an extended SHUTDOWN. 'If the outage. involved l addition:of spent fuel'to the spent fuel pool, the decay. heat load in the spent fuel pool shall be determined to be less than a limiting

-value.. This limiting value is that heat load for which the spent fuel pool make-up system can maintain the pool temperature less than or  ;

equal to 150*F in the event.that normal ~ pool cooling cannot be provided. The reactor is to remain SHUTDOWN until the above restriction is met.

The procedure for a normal cold start-up shall be as follows:

(a) 'A start-up checklist shall be followed prior to beginning the actual start-up 90 that applicable equipment and systems shall be in condition for start-up. Containment sphere integrity provisions shall be in effect.

(b). Each control rod shall be exercised and scrammed as a check of the control rod hydraulic system and the reactor safety system. A coupling verification check shall be included prior to or during start-up.

(c) The start-up checklist shall be reviewed and approved by the Shift Supervisor prior to start-up.

Proposed TSB0387-0015-WLO4-

-o .

- 92 9.0' ' INSERVICE-INSPECTION AND TESTING 9.1 APPLICABILITY Applies to inservice inspection and testing of the reactor vessel and other ASME Code Class 1, Class 2 and Class 3 system components.

9.2 OBJECTIVE To insure the integrity of the Class 1, Class 2 and Class 3 piping systems and components.

9.3 SPECIFICATIONS

a. Inservice Inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance.with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where spe-cific written relief has been granted by the Commission pursuant to 10 CFR. 50, Section 50.55a(g)(6)(1), and where provisions of Sections 11.4.1.4, 4.1.5 and 11.4.3.4 take precedence.

b. Sufficient records of each inspection shall'be kept to allow comparison and evaluation of future tests. (See also Sections 6.9.3 and 6.10.2.g.) l

c. The inservice inspection program shall be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven practical, and the conclusions of the evaluation shall be used as appropriate to update the inspection program.

d. A surveillance program to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.1.1(h) of these Technical Specifications, i

9.4 BASIS The inspection program implementsSection XI of the ASME Boiler and Pressure Vessel Code to the maximum extent practical. It is recognized that plant desigt. and construction were completed approximately seven years prior to the development of Section XI and it is, thereforu, not possible to comply fully with the code.

Proposed TSB0387-0015-NLO4 l

+

.i ADMINISTRATIVE CONTROLS s

6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall plant operation j and shall delegate in writing the succession to this responsibility during his absence.

I 6.1.2 The Shift Supervisor shall be responsible for the shift command j function. A Management directive to this effect shall be issued j annually by the Vice President - Nuclear Operations.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for plant management and techniral support shall be as shown in Figure 6.2-1.

PLANT STAFF 6.2.2 The plant organization shall be as shown in Figure 6.2-2 and:

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.

1

c. At least two licensed Operators shall be present in the control .j room during reactor start-up (to a power level 25 percent), j 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 reactor.*

e. All core alterations, after the initial fuel loading, shall i cither be performed by a licensed Reactor Operator under the j general supervision of a Senior Reactor Operator or a nonlicensed W Operator directly supervised by a licensed Senior Reactor  !

Operator (or Senior Operator Limited to Fuel Handling) who has l no other concurrent responsibilities during this operation. j I

f. A Fire Brigade of at least 5 members shall be maintained on site at all times.* The Fire Brigade shall not include 2 members of li the minimum shift crew necessary for safe shutdown of the plant )

and any personnel required for other essential functions during  ;

a fire emergency. )

I l

• Aadiation Protection coverage and Fire Brigade composition may be less than I the minimum requirements for a period of time not to exceed two hours in order l to accommodate unexpected absence provided immediate action is taken to j restore the minimum requirements.

103 Proposed TSB0387-0015-NLO4 1

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/

ADMINISTRATIVE CONTROLS

g. Administrative procedures shall be developed and implemented to limit the working hours of plant staff 1ho perform safety-related operation functions; ie, sculor reactorforerators, reactor operators, auxiliary operators, health physicists and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

(1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

(2) An individual should not be permitted to work more than l 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in j any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day  !

period, all excluding shift turnover time. 1 (3) A break, including shift turnover time, of at least eight hours should be. allowed after continuous work periods of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> duration.

(4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation fram the above guidelines shall be authorized by the Plant Manager or his alternate (Production and Performance or l Engineering and Maintenance Superintendents), or higher levels of Management, in accordance,with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual  !

overtime will be reviewed monthly by the Plant 11anager or his l designee to assure that excessive hours have not been assigned.

Routine deviations from the above guidelines is not authorized.  ;

1 1

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l TSB0387-0015-NLO4

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9 g CONSUMERS POWER COMPANY

. PLANT ORGAN 1ZATION Plant Manager (a)

Nuclear-Assurance Off-Site. ,

I QA . , _ _ . Plant Review Superintendent Committee QC Supervisor I

. Chem /HP Production and Engineering & Planning and Admin I Superintendent Performance Maintenance Services Superintendent Superintendent Superintendent y Other Operations Supervisor Services SR0(b)

Shift Supervisors - SRO Figure 6.2-2 A, To support the above Plant organization, personnel knowledgeable in the following areas identified in ANS1 N18.7-1976/ ANS 3.2 will report at the discretion of the Plant Manager:

l

1. Nuclaar Power Plant Mechanical, Electrical and Electronic Systems

2. Nuclear Engineering

3. Chemistry and Radiochemistry

4. Radiation Protection (Reports to Chem /EP Superintendent)

A single individual may be qualified and perform in more than one discipline.

B. The Security Force will be supervised as described in the Plant Security Plan.

C. Quality Assurance / Control activities will be in accordance with Consumers Power Company's Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A, as revised).

(s) Responsible for the Plant Fire Protection Program implementation.

-(b)Either the Production and Performance Superintendent or the Operations Supervisor will hold an SRO and meet the other requirements of 6.3.1 of these Technical Specifications (as applicable to Operations Manager in ANSI N18.1). The individual holding an SRO shall be responsible for directing the activities of licensed operators.

(SRO - Senior Reactor Operator License) 105 Proposed TSB0387-0015-NLO4

} .

ADMINISTRATIVE CONTROLS __

6.3 PLANTLSTAFF' QUALIFICATIONS _

6.3.1 Each me:raer of the plant staff shall meet or exceed the minimum qualifications of ANS1 N18.1-1971 for comparable positions.

6.3.2 - Either the Chemir.,try and health Physics Superintendent or the Chemistry and Radiction Protection Supervisor shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.y 6.3.3 The On-call Te:hnical Advisor (OTA) 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 transiento and accidents.

6.4 TRAINJLKG

( 6.4.1 A Ietraining and replacement training program for the plant staff shall be maintain (d under the direction of the Director of Nuclear Trait.ing and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55. l 6.4.2 The Manager of Inicrmation and Operations is responsible for the l development, revision, approval and splementation of the Fire brigade training program. This tr.: ung shall, as practicable, meet or exceed the requirements of Se' 27 of the NFPA Code-1975.

Fire Brigade training drills ab oe held at least quarterly.

6.5 REVIEW AND AUDII 6.5.1 PLANT REVIEW COMMITTEE (PRC)

FUNCTION 6.5,1.1 The Plant Review Committee (PRC) shall function to advise the Plant Manager en all matters related to nuclear safety. l

_ COMPOSITION 6.5.1.2 The PRC shall be composed of:

Chairman:' Plant Manager or Designated Alternate Appointed by the Plant Manager Member: Froduction & Performance Superintendent Member: Planning & Admin Services Superintendent Member: Engineering & Maintenance Superintendent Member: Operations Supervisor Member: Instrument and Control Supervisor Member: Reactor Engineer Member: Chemistry and Health Physics Superintendent Member: Shift Supervisor Member: Technical Engineer For the purpose of this section, " Equivalent," as utii.ized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) Formal schooling in science 1 ,

N engineering or (b) operational or technical experience / training in nuclear J

power.

107 Proposed

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vt .'

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis. However, no more than two alternates shall participate as voting members at any one time in PRC activities.

MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month, with special meetings as required.

QUOkUM 6.5.1.5 A quorum for PRC shall consist of the Chairman and four (4) voting members.

RESPONSIBILITIES 6.5.1.6 The PRC shall be responsible for:

a. Review of: (1) all procedures required by Technical Specification 6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety. l

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

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

d. Eeview of all proposed changes or modifications to plant  ;

systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and forwarded to the Vice President Nuclear Operations and to the Director - Nuclear Safety.)

f. Review of plant operations to detect potential nuclear ,

safety hazards. ]

g. Review of reportable events as defined in Section 1.2.14.

i l

h. Performance of special reviews and investigations and reports thereof as requested by the Plant Manager or Chairman of NSB.

l ,

1. Review of the Site Emergency Plan and implementing procedures.

108 Proposed TSB0387-0015-NLO4

. _ _ _ ______________A

I Ausril'ISTRATIVE CONTROLS RESPONSIBILITIES (Contd)

j. Review of any accidental, unplanned or uncontrolled  !

radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Plant Manager and to the Nuclear Safety Board (NSB).

PRC review may be performed through a routing of the item subject to the requirements of Specification 6.5.1.7.

AUTHORITY 6.5.1.7 The PRC shall:

a. Recommend in. writing to the Plant Manager approval or l disapproval of items considered under Specifications 6.5.1.6.a through d. above.

b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6.a through e above constitutes an unreviewed safety question.

c. Provide written notification with n 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Operations and to the Vice Chairman of NSB of any disagreement between the PRC and the Plant Manager; however, the Plant Manager shall have l responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.

The PRC Chairman may recommend to the Plant Manager approval of l those items identified in Specifications 6.5.1.6 a, through d. above based on a routing review provided the following conditions are met:

(1) at least five PRC members, including the Chairnan and no more than 2 alternates, shall review the item, concur with determination as to whether or not the item conet'tutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.

The item shall be reviewed at a PRC meeting in the event.that:

(1) comments are not resolved; or (2) the Plant Manager overrides l the recommendations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was a reportable event as defined in 10 CFR 50.73.

RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSB.

109 Proposed TSB0387-0015-NLO4

6.5.2 NUCLEAR SAFETY BOARD (NSB) 6.5.2.1 The Nuclear Safety Board is responsible for maintaining a continuing examination of nuclear sa!.ety-related corporate and plant activities and defining opportunities for policy changes related to improved nuclear safety performance. The NSB shall operate in accordance with a written charter approved by the Vice President - Nuclear Operations, I which designates the membership, authority, and rules for conducting I

the meetings.

FUNCTION 6.5.2.2 The NSB shall function to provide review of designated activities in the areas specified in Specification 6.5.2.3.

COMPOSITION 6.5.2.3 The NSB shall consict of members appointed by the Vice President -

Nuclear Operations. NSB shall be chaired by the Director - Nuclear Safety, or a duly appointed alternate.

Collectively, the personnel appointed to NSS shall be competent to conduct reviews in the following areas:

a. Nuclear Power Plant Operations

b. Nuclear Engineering

c. Chemistry and Radiochemistry

d. Metallurgy

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical and Electrical Engineering

h. Quality Assurance Practices An individual appointed to NSB ma;r possess expertise in more than one of the above specialties These individuals should, in general, have had professional experience in t.h<.tr specialty at or above the Senior Engineer level.

ALTERNATE MEMBERS 6.5.2.4 Alternate members may be appointed in writing by the Vice President >

Nuclear Operations to src in place of members during any legitimate and unavoidable absencee. The qualifications of alternate members shall be similar to those of members. ,

1 CONSULTANTS )

6.5.2.5 Consultants shall be utilized as determined by the NSB Chairman to provide expert advice to the NSB. NSB members are not restricted as to sources of technical input and may call for separate l investigation from any competent source.

110 Proposed TSB0387-0015-NLO4 l

9

.. . ADMINISTRATIVE CONTROLS- 3 MEEIlNG FREQUENCY 6.5.2.6' NSB shall meet at-least once per calendar quarter during the initial year of facility operation following fuel loading and at least once every six months thereafter.

QUORUM 6.5.2.7 A quorum of NSB shall consist of the Chairman and four (4) members. j l' No more than a minority of the quorum shall have line responsibility for operation of the facility. It is the responsibility of the L Chairman to ensure that.the quorum convened for a meeting conta1ns appropriately qualified members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.

6.5.2.8 RESPONSIBILITIES REVTEW 6

'.5.2.8.1 NSB shall be responsible for the review of:

a. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety,

b. All reportable events and other violations (of applicable statues, codes, regulations, orders, Technical Specifications, license requirements or of internal procedures or instructions)'having nuclear safety significance.

c.- Issues of safety significance identified by the Plant Manager, the NSB Chairman, Director - Nuclear Safety or the PRC.

l

d. Proposed changes in the operating license or Appendix "A" Technical Specifications.

e. The results of actions t aken to correct deficiencies identified by the audit program specified in Specification 6.5.2.8.2 at least once every six months.

f. Safety evaluations for changes to procedures, equipment or systems and teste or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question, i

g. Maintain cognizance of PRC activities through ISEG attendance at scheduled and spec!al PRC meetings or through review of PRC meeting minutes.

111 Proposed l

TSB0387-0015-NLO4

AUDITS 6.5.2.8.2 Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of NSB. These audits shall encompass:

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

b. The performance, training and qualifications of the entire facility staff at least once per 12 months.

c. The performance of activities required by the operational quality assurance program (CPC-2A QAPD) to meet the criteria of Appendix "B," 10 CFR 50, at least once per 24 months,

d. The Site Emergency Plan and implementing procedures at least once per 12 months.

e. The Site Security Plan and implementing procedures (as required by the Site Security Plan) at least once per 12 months,

f. Any other area of plant operation considered appropriate by NSB or the Vice President - Nuclear Operations.

g. The plant Fire Protection Program and implementing procedures at least once per 24 months,

h. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.

1. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

j. The radiological environmental monitoring program and the results thereof at least once per 12 months.

Audit reports encompassed by 6.5.2.8.2 above shall be forwarded to the NSB Chairman and Management positions responsible for the areas audited within thirty (30) days after completion of the audit.

AUTHORITY 6.5.2.9 The NSB Chairman shall report to and advise the Vice President - Nuclear Operations of significant findings associated with NSB activities and of recommendations related to improving plant nuclear safety performance.

112 Proposed TSB0387-0015-NLO4

<r o .

... ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of NSB activities shall be prepared and distributed as indicated below:

a. Minutes of each NSB meeting shall be prepared cnd forwarded to the Vice President - Nuclear Operations and each NSB member within approximately two weeks following completion of the review.

b If not included in NSB meeting minutes, reports of reviews encompassed by Specification 6.5.2.8.1 shell be prepared and forwarded to the Vice President - Nuclear Operations within approximately two weeks following completion of the review.

6.6 (Deleted) 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a. The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).

b. The safety limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Commission in accordance with 10 CFR 50.36, as well as to the Vice President - Nuclear Operations and to the Chairman - NSB.

c. A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification. (The safety limit violation and the report shall be reviewed by the PRC.)

d. The report shall be submitted within 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36), to the Vice President - Nuclear Operations and to the Chairman - NSB.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained for all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedures shall meet or exceed the requirements of ANSI N18.7, as endorsed by CPC-2A.

6.8.2 PRC is responsible for the review of each procedure of 6.8.1 above, and changes thereto (except for Security Implementing Procedures which are reviewed and approved in accordance with the Site Security Plan). l The Plant Manager shall approve such procedures and changes prior to impicmente. tion.

1 113 Proposed TSB0387-0015-NLO4 N___-_____

1 9

t ADMINISTRATIVE CONTROLS 6.8.3 'lemporary changes to procedures of 6.8.1 cbove may be made provided:

a. Ths intent of the original procedure is not altered.

b. The change is approved by two members (or designated alternates) of the PRC, at least one of whom holds a Senior Reactor Operator's License.

c. The change is documented, reviewed by the PRC at the next regularly scheduled meeting and approved by the Plant Manager. ,

6.9 REPORTING REQUIREMENT ROUTINE REPORTS 6.9.1 In additien to the applicable reporting requirements of Title 10, Code of Federal Regulationat the following reports shall be submir.ted to the Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with copies to the Region Administrator and the Resident Inspector in accordance with 10CFR50.4.

START-UP REPORT 6.9,1.1 A summary report of plant start-up and power escalation testing shall be submitted following: (1) receipt of an operating license, (2) amendment to the license involv$ng a planned incresue in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier apd (4) modifications that may have significantly altered the nuclear, thermal or hydratile performance of the plant.

6.9.1.2 The start-up report shall address each of the tests identified in the Final Hazards Summary Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the_ test program and a compar1 con of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additiona? specific details required ir license conditions based on other commitments shall be included in this report.

6.9.1.3 Start-up reports shall be submitted within: (1) 90 days following completion of the start-up 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 start-up report does not cover all three events (ie. initial criticality, completion of start-up test program.and rssumption or commencement of commercial operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

114 Proposed TSB0387-0015-NLO4

E4 : '8

. -ADMINIS1RATIVE CONTROLS ANNUAL REPORTS 6.9.1.4 An annual. report covering occupational exposure for the' previous calendar year shall be submitted prior to March 1 of each year.

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 associated manrem exposure according to work and job functions;l eg, reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD or film badge measurements. Small exposures totaling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics cnd shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

(Section 6.9.1.7 Deleted)

(Section 6.9.1.8 Deleted)

(Section 6.9.1.9 Del 2ted)

I This tabluation supplements the requirement of 520.407 of 10 CFR, Part 20.

115 Proposed

. TSB0387-0015-NLO4

• ADMINISTRATIVE CONTROLS i

.1 6.9.3 SPECIAL REPORTS Special reports shall'be submitted to the Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555 with copies to the-Region Administrator and the Resident Inspector in accordance

- with 10CFR50.4 within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable Technical Specifications section:

a. Inservice inspection reports,

b. Fire system reports.

c. High-range containment gamma monitoring system reports.

d. Stack gas monitaring system reports.

6.10. RECORD RETENTION I

(Records not previously required ;o be retained shall be retained as required-below commencing January 1, 1976.)

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.

120 Proposed TSB0387-0015-NLO4

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a e . INSTRUMENTATION FIRE DETECTION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-8 shal). be OPERABLE.

APPLICABILITY: At all times when the equipment in the area is required be to OPERABLE.

ACTIONS:

With the number of instruments OPERABLE less than required by Table 3.3-8;

a. Within one (1) hour, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once per hour, and

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.2, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within the next l 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above fire detection instruments shall be demonstrated OPERABLE:

a. Once per six months by a CHANNEi. FUNCTIONAL TEST except for detectors located in the recirculation pump room which shall be tested at each refueling outage; and l

b. Once per 31 days by verifying proper alignment of power sources to the circuits.

150 Proposed TSB0387-0015-NLO4

e,7

.,; c a o PLANT SYSTEMS FILE SUPPRESSION WATER SYSTEM-

> LIMITING CONDITION FOR OPERATION 3.7.11.1 THE FIRE SUPPRESSION WATER SYSTEM SHALL BE OPERABLE WITH:

.a.- Both the electric and diesel driven fire pumps each with a capacity of.1000 gpm, their discharge aligned to the fire suppression header and supplying sprinkler and hose systems described in 3.7.11.2 and 3.7.11.5.

b. Level of the' Intake Bay above the 570' elevation.

c. Automatic starting of the pumps on decaying fire system i pressure.

l APPLICABILITY: At All times.

ACTIONS:

a. With the Fire Suppression Wat~ar System inoperable, restore the i inoperable equipment to OPERABLE status with1n 7 days or, in I li2u of any other report required by Specification 6.9.2, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within the next 30 days outlining the l plans and procedures to be used to provide for the loss of redundancy in this system.

t, Comply with Specification 11.3.1.4D.

c. If both fire pumps (electric and diesel) or the piping systems are inoperable:

1. Initiate procedures to provide a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by not1fying the Charlevoix Fire Department to standby, and l i

2. Restore thn inoperable fire pump or piping system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.2, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within the next 30 days outlining the action taken, the ccuse of the inoperability and the plans and schedule for restoring che pump or piping system to OPERABLE status.

I 152 Proposed I

TSB0387-0015-NLO4 i

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