ML20059B856

Amend 84 to License NPF-49,removes Requirements from License & TS Pertaining to Fire Protection Program & Places Same Requirements in Operating Procedures

ML20059B856
Person / Time
Site:	Millstone
Issue date:	10/25/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20059B858	List: ML20059B856 ML20059B863
References
NPF-49-A-084 NUDOCS 9310290120
Download: ML20059B856 (36)

Text

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UNITED STATES I

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E NUCLEAR REGULATORY COMMISSION 4I WASWNGTON. D.C. 20666-0001

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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. NPF-49 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated July 31, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act), and the Comission's rules and regulations set,

forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application,.the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

)

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9310290120 931025 PDR ADOCK 05000423 p

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E.

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 84

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The license is further amended by deleting paragraph 2.C.(3)*, and by adding paragraph 2.H* to read as follows:

H.

Fire Protection (Section 9.5.1. SER. SSER2. SSER4. SSERS)

Northeast Nuclear Energy Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER (NUREG-1031) issued July 1984 and Supplements Nos. 2, 4, and 5 issued September 1985, November 1985 and January 1986, respectively, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l

oh i9. Stolz, Direct Pr ject Directorate I-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:

1.

Pages 3, 8, and 9 of License 2.

Changes to the Technical Specifications Date of Issuance: October 25, 1993

• Pages 3, 8 and 9 are attached, for convenience, for the composite license to reflect this change.

, (Next Page is 8)

(3)

NNEC0, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required:

(4)

NNEC0, -pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

NNECO, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operations of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provision of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power level Northeast Nuclear Energy Company is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The technical specifications contained in Appendix A revised through Amendment No.

, and the Environmental Protection Plan contained in Appendix B,

both of which are attached hereto, are hereby incorporated into this license.

Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

DELETED (4)

Salem ATWS Events Generic letter 83-28 NNECO shall submit responses to and implement the requirc ants of Generic Letter 33-28 Salem ATWS Events on a schedule which is consistent with that given in their November 8, 1983 letter as modified by their letters dated March 16, 1984 and Sep' ember 5, 1985.

Amendment No. 42, 68,84

, D.

Exemptions from certain requirements of Appendix J 10 CFR Part 50 (Section 6.2.6, SSER 4) and from a portion of the requirements of General Design Criterion 4 (Section 3.9.3.1, SSER 4) of Appendix A to 10 CFR Part 50 have previously been granted.

See Safety Evaluation Report Supplement 4,

November 1985.

With these exemptions the facility will operate, to the extent authorized

herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

" Millstone Nuclear Power Station Physical Security Plan," with revisions submitted through Mar-:h 29,1988; " Millstone Nuclear Power Station Suitability, Training and Qualification Plan," with revision submitted through July 21, 1986; and " Millstone Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through October 30, 1985.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

F.

Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Northeast Nuclear Energy Company shall report any violations of the requirements contained in Section 2.C of this license in the following manner:

initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c) and (e).

l l

G.

The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

)

l H.

Fire Protection (Section 9.5.1 SER. SSER 2. SSER4. SSER5)

Northeast Nuclear Energy Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER (NUREG-1031) issued July 1984 and Supplements l

l Nos.

2, 4,

and 5 issued September 1985, November 1985 and j

January 1986, respectively, subject to the following provision:

a Amendment No.19,84

.g.

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

I.

This license is effective as of the date of issuance and shall expire at Midnight on November 25, 2025.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by H. R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments / Appendices:

1.

Appendix A - Technical Specifications (NUREG-ll76) 2.

Appendix B - Environmental Protection Plan Date of Issuance: January 31, 1986 j

l i

Amendment No.84

L ATTACHMENT TO LICENSE AMENDMENT NO.84 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change, Remove Insert i

i vi vi x

x xv xv 1-3 1-3 3/4 3-64 3/4 3-64 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7-31 3/4 7-32 3/4 7-32 3/4 7-33 3/4 7-33 i

3/4 7-33 3/4 7-33 3/4 7-36 3/4 7-36 3/4 7-37 3/4 7-37 3/4 7-38 3/4 7-38 3/4 7-39 3/4 7-39 3/4 7-40 3/4 7-40 3/4 7-41 3/4 7-41 3/4 7-42 3/4 7-42 3/4 7-43 3/4 7-43 B3/4 3-5 B3/4 3-5 B3/4 7-7 B3/4 7-7 B3/4 7-8 B3/4 7-8 6-2 6-2 6-5 6-5 6-6 6-6 6-8 6-8

INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 ACTI0N.......................................................

1-1 1.2 ACTUATION LOGIC TEST.........................................

1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST..............................

1-1 1.4 AXIAL FLUX DIFFERENCE........................................

1-1 1.5 CHANNEL CALIBRATION..........................................

1-1 1.G CNANNEL CHECK................................................

1-1 1.7 CONTAINMENT INTEGRITY........................................

1-2 1.8 CONTROLLED LEAKAGE...........................................

1-2 1.9 CORE ALTERATIONS.............................................

1-2 1.10 DOSE EQUIVALENT I-131........................................

1-2 1.11 E - AVERAGE DISINTEGRATION ENERGY............................

1-2 1.12 ENCLOSURE BUILDING INTEGRITY.................................

1-3 1.13 ENGINEERED SAFETY FEATURES RESPONSE TIME.....................

1-3 l.14 DELETED 1.15 FREQUENCY N0TATION...........................................

1-3 1.16 IDENTIFIED LEAKAGE...........................................

1-3 1.17 MASTER RELAY TEST............................................

1-3 1.18 MEMBER (S) 0F THE PUBLIC......................................

1-4 1.19 OPERABLE - OPERABILITY.......................................

1-4 1.20 OPERATIONAL MODE - M0DE......................................

1-4 1.21 PHYSICS TESTS................................................

1-4 1.22 PRESSURE BOUNDARY LEAKAGE....................................

1-4 1.23 PURGE - PURGING..............................................

1-4 1.24 QUADRANT POWER TILT RATI0....................................

1-5 1.25 RADI0 ACTIVE WASTE TREATMENT SYSTEMS..........................

1-5 1.26 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM).................................

1-5 1.27 RATED THERMAL P0WER..........................................

1-5 1.28 REACTOR TRIP SYSTEM RESPONSE TIME............................

1-5 1.29 REPORTABLE EVENT.............................................

1-5 1.30 SHUTDOWN MARGIN..............................................

1-5 1.31 SITE B0VNDARY................................................

1-6 l

MILLSTONE - UNIT 3 i

Amendment No. 84 0082

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION MG1 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES............

3/4 3-32 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

3/4 3-36 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations...............

3/4 3-42 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT 0PERATIONS....................................

3/4 3-43 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS....................

3/4 3-45 Movabl e Incore Detectors................................

3/4 3-46 Seismic Instrumentation.................................

3/4 3-47 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION...................

3/4 3-48 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-49 Meteorological Instrumentation..........................

3/4 3 ~C TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............

3/4 3-51 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-52 Remote Shutdown Instrumentation.........................

3/4 3-53 TABLE 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION......................

3/4 3-54 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................

3/4 3-58 Accident Monitoring Instrumentation.....................

3/4 3-59 TABLE 3.3-10 ACCIDENT MONITORING-INSTRUMENTATION.................

3/4 3-60 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-62 TABLE 3.3-11 DELETED

\\

Loose-Part Detection System.............................

3/4 3-68 Radioactive Liquid Effluent Monitoring Instrumentation..

3/4 3-69 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.....................................

3/4 3-70 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

3/4 3-72 Radioactive Gaseous Effluent M...itoring Instrumentation.

3/4 3-74 MILLSTONE - UNIT 3 vi Amendment No. 84 cons j

INDEX l

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION fAGE q

TABLE 3.7-3 STEAM LINE SAFETY VALVES PER L00P......................

3/4 7-3 1

Auxiliary Feedwater System...............................

3/4 7-4 Demineralized Water Storage Tank.........................

3/4 7-6 Specific Activity........................................

3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................

3/4 7-8 Main Steam Line Isol ation Val ves.........................

3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-10 3/4.7.3 REACTOR PLANT COMP 0NENT COOLING WATER SYSTEM.............

3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.....................................

3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK.......................................

3/4 7-13 3/4.7.6 FLOOD PROTECTION.........................................

3/4 7-14 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................

3/4 7-15 3/4.7.8 CONTROL ROOM ENVELOPE PRESSURIZATION SYSTEM..............

3/4 7-18

'n.7.9 AUXILIARY BUILDING FILTER SYSTEM.........................

3/4 7-20 3/4.7.10 SNUBBERS.................................................

3/4 7-22 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST...........

3/4 7-27 1

3/4.7.11 SEALED SOURCE CONTAMINATION..............................

3/4 7-28 3/4.7.12 DELETED j

TABLE 3.7-4 DELETED 1

TABLE 3.7-5 DELETED 3/4.7.13 DELETED 3/4.7.14 AREA TEMPERATURE M0NITORING..............................

3/4 7-44 TABLE 3.76 AREA TEMPERATURE MONITORING...........................

3/4 7-45 MILLSTONE - UNIT 3 x

Amendment No. A2,84 0084

INDEX BASIS

+

I SECTION PA31 3/4.7.11 SEALED SOURCE CONTAMINATION.........................

B 3/4 7 -

3/4.7.12 DELETED 3/4.7.13 DELETED 3/4.7.14 AREA TEMPERATURE M0NITORING.........................

B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION............................

B 3/4 8-1 3.4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES..............

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 1

3/4.9.1 BORON CONCENTRATION..................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................

B 3/4 9-1 3/4.9.3 DECAY TIME...........................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS....................

B 3/4 9 3/4.9.5 COMMUNICATIONS.......................................

B 3/4 9-1 3/4.9.6 REFUELING MACHINE....................................

B 3/4 9-2 j

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS..............

B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION........

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.......

B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL-AND STORAGE P00L.........................................

B 3/4 9-3 3/4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEM..................

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS i

3/4.10.1 SHUTDOWN MARGIN......................................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS. B 3/4 10-1 3/4.10.3 PHYSICS TESTS.........................................

B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS.................................

B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN.................

B 3/4 10-l' l

4 MILLSTONE - UNIT 3 xv Amendment No. 84 0085

DEFINITIONS i

ENCLOSURE BUILDING INTEGRITY 1.12 ENCLOSURE BUILDING INTEGRITY shall exist when:

a.

Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, b.

The Supplementary Leak Collection and Release System is OPERABLE, and c.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.

ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

1.14 Deleted FRE0VENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as-pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay.

The MASTER RELAY TEST shall include a continuity check of each associated slave relay.

MILLSTONE - UNIT 3 1-3 Amendment No.84 0086

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INSTRUMENTATION BASES REMOTE SHUTDOWN INSTRUMENTATION (Continued) instrumentation, control, and power circuits and transfer switches necessary to eliminate effects of the fire and allow operation of instrumentation, con-trol and power circuits required to achieve and maintain a safe shutdown con-dition are independent of areas where a fire could damage systems normally used to shut down the reactor.

This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR fart 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. The instrumentation in-cluded in this specification are those instruments provided to monitor key variables, designated as Category 1 instruments following the guidance for classification contained in Regulatory Guide 1.97, Revision 2, "Instrumenta-tion for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident."

In the event more than four sensors in a Reactor Vessel Level channel are i

inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and reactor vessel head are removed.

It is not feasible to repair a channel i

except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core.

If only one channel is inoperable, it i

should be restored to OPERABLE status in a refueling outage as soon as reason-

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ably possible.

If both channels are inoperable, at least one channel shall be restored to OPERABLE status in the nearest refueling outage.

3/4.3.3.7 Deleted.

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MILLSTONE - UNIT 3 8 3/4 3-5 Amendment No. 7, 77, 84 0177

i PLANT SYSTEMS BASES 3/4.7.11 SEALED SOURCE CONTAMINATION (Continued) plutonium.

This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4.7.12 Deleted

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MILLSTONE - UNIT 3 B 3/4 7-7 Amendment No. EE,84 0089

PLANT SYSTEMS BASES 3/4.7.13 Deleted 3/4.7.14 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.

Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY. The temperature limits include an allowance for instrument error of 12.2*F.

MILLSTONE - UNIT 3 B 3/4 7-8 Amendment No. EE,84 0089

ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued) b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; c.

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

d.

A Health Physics Technician

• shall be on site when fuel is in the reactor; e.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fu~el Handling who has no other concurrent responsibilities during this operation; f.

Deleted g.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No.

82-12).

• The Health Physics Technician composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

MILLSTONE UNIT 3 6-2 Amendment No. JJ JJ, 84 0178

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Station Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.

6.4.2 Deleted.

l 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Nuclear Unit Director on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PORC shall be composed of the:

Chairperson:

Nuclear Unit Director Vice Chairperson and Member:

Operations Manager Member:

Maintenance Manager Member:

Instrument and Controls Manager Member:

Reactor Engineer Member:

Radiation Protection Supervisor or Chemistry Supervisor Member:

Engineering Manager Member:

Staff Engineer MILLSTONE - UNIT 3 6-5 Amendment No. JE, JJ,84 0174

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ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one l

time.

1 MEETING FRE0VENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.

1 OVORUM 6.5.1.5 The quorum of the PORC shall consist of the Chairperson or Vice Chairperson or Nuclear Station Director and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

a. Review of:

(1) all procedures, except common site procedures, required by Specification 6 8 and changes thereto, and (2) any other i

roposed procedures or chanies thereto as determined by the Nuclear i

BnitDirectortoaffectnuclearsafety;

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

c. Review of all proposed changes to Sections 1.0-5.0 of these Technical Specifications;

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, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence, to the Executive Vice President-Nuclear and to the Chairperson of the Nuclear Review Board;

f. Review of all REPORTABLE EVENTS; i

g. Review of facility operations to detect potential safety hazards;

h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairperson of the Nuclear i

i Review Board or the Nuclear Station Director; and

1. Render determinations in writing if any item considered under Specification 6.5.1.6a. through d. above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question, or requires a significant hazards consideration determination.

j. Review of Unit Turbine Overspeed Protection Maintenance and Testing Program and revision thereto.

k. Review of the Fire Protection Program and implementing procedures.

l MILLSTONE - UNIT 3 6-6 Amendment No. M, y,84 0012

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, ADMI.NISTRATIVE CONTROLS 000 RUM i

6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice Chairperson and five members including alternates.

RESPONSIBILITIES 6.5.2.6 The SORC shall be responsible for:

1 all common site procedures required by Specifica-Review of (d) changes thereto, (2) h a.

tion 6.8 an any other proposed procedures or changes thereto as determined by t e Nuclear Station Director to affect site nuclear safety; b.

Review of all proposed changes to Section 6.0 " Administrative Controls" of these Technical Specifications c.

Performance of special reviews and investigations and reports as requested by the Chairperson of the Site Nuclear Review Board; d.

Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Chairperson of the Site i

Nuclear Review Board; e.

Review of the Emergency Plan and implementing procedures, and sub-mittal of recommended changes to the Chairperson of the Site Nuclear Review Board; f.

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

Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety; and h.

Render determinations in writing or meeting minutes if any item 6.5.2.6(59 or 10CFR50.92 constitutes a) through (g) above, as considered under Specification appropriate and as provided by 10CFR50.

4 an unreviewed safety question or requires a significant hazards consideration determination.

i.

Review of the common site Fire Protection Program and implementing procedures.

AUTHORITY 6.5.2.7 The 50RC shall:

a.

Recommend to the Nuclear Station Director written approval or disapproval in meeting :ninutes of items considered under Specification 6.5.2.6(a) through (g) above, and b.

Provide immediate written notification or meeting minutes to the Executive Vice President-Nuclear and the Chairperson of the Site Nuclear Review Board of disagreement between the SORC and the Nuclear Station Director; however, the Nuclear Station Director shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

FECORDS 6.5.2.8 The 50RC shall maintain written minutes of each meeting and copies shall be provided to the Executive Vice President-Nuclear and Chairperson of the Site Nuclear Review Board.

MILLSTONE - UNIT 3 6-8 Amendment No. 77,84 0175