ML20202E836

Amend 46 to License DPR-22,modifying Immediate Notification Requirements for Operating Nuclear Power Reactors,Ler Sys & Table 6.1-1, Min Shift Crew Compositon

ML20202E836
Person / Time
Site:	Monticello
Issue date:	07/01/1986
From:	Rajender Auluck Office of Nuclear Reactor Regulation
To:
Shared Package
ML20202E840	List: ML20202E836 ML20202E848
References
NUDOCS 8607150026
Download: ML20202E836 (22)

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UNITED STATES NUCLEAR REGULATORY COMMISSION g

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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-22 1.

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

A.

The application for amendment by Northern States Power Company (the licensee) dated September 14, 1984, and clarified on January 10, 1986 and May 7, 1986, 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; 4

B.

The facility will. operate in conformity with the application, the provisions of the Act, and the rule; and regulations of the Comission; C..There is reasonable assurance (1) that the activities authorized i

by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be l

conducted in compliance with the Comission'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 4

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements i

have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby i

amended to read as follows:

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w 2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 46, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 9.-

Rajender Auluck, Project Manager BWR Project Directorate #1 Division of BWR Licensing

Attachment:

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Changes to the Technical Specifications Date of Issuance:

July 1, 1986 i

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ATTACHMENT TO LICENSE AMENDMENT N0. 46 FACILITY OPERATING LICENSE N0. DPR I DOCKET NO. 50-263 i

Revise Appendix "A" Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT i

iy iy Sa Sa 194 194 195 195 198 198 198a 198a 198b 198b 198f 198f 223 223 225 225 227 227 227a 227a 1

227b 227b 2291 2291 l

234 234 235 235 I

236 236 i

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239 239 240 240 4

242 242 250 250 1

251 251 252 252 253 253 i

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{agg 3.13 and 4.13 Fire Detection and Protection Systems 223 A.

Fire Detection Instrumentation 223 B.

Fire. Suppression Water System 224 C.

Bose Stations 226 D.

Yard Hydrant Mose Houses 227 E.

Sprinkler Systems 227a F.

Raion Systems 227b G.

Fenetration Fire Barriers 227b 3.13 Bases 228 4.13 Bases 229 3.14 and 4.14 Accident Monitoring Instrumentation 229a 3.14 and 4.14 Bases 229e 3.15 and 4.15 Inservice Inspection and Testing 229f 3.15 and 4.15 Bases 229s 3.16 and 4.16 Radiation Environmental Monitoring Program 229h A.

Sampling and Analysis 229h B.

Land Use Census 229j C.

Interlaboratory Comparison 229k 3.16 and 4.16 Bases 229t j

5.0 DESIGN FEATURES 230 5.1 Site 230 5.2 Reactor 230 5.3 Reactor Vessel 230 5.4 Containment 230 5.5 Puel Storage 231 5.6 Seismic Designs 231 6.0 ADMINISTRATIVE CONTROLS 232 6.1 Organization 232 6.2 Review and. Audit 237

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6.3 Special Inspection and Audits 243 6.4 Action to be taken if a Safety Limit is Exceeded 243 6.5 Plant Operating Procedures 244 6.6 Plant Operating Records 246 l

6.7 Reporting Requirements 248 6.8 Environmental Qualification 253 l

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Amendment No. 15, 37, 46 gy

All.

Source Check - A Source Check is the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

AI.

Purging - Purging is the controlled process of discharging air or gas from a confinement to maintain temperature pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

AJ.

Venting - Venting is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required.

AK.

Dose Equivalent I-131 - Dose Equivalent I-131 is the concentration of I-131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, 1-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculatioa of Distance Factors for Power and Test Reactor Sites" or in NRC Regulatory Guide 1.109, Rev.1, October,1977.

AL.

Offgas Treatment System - The Offgas Treatment System is the system designed and installed to reduce radioactive gaseous ef fluents by collecting primary coolant system of fgases from the primary system and providing for delay or holdup for the purpose of reducing the total radio-activity prior to release to the environment.

AM.

Members of the Public - Means all persons who are not occupationally associated with the plant.

This category does not include employees of,ttue utility, its contractors, or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make i

deliveries. This category does include persons who use portions of the site for recreational, l

occupational, or other purposes not associated with the plant.

4 AN.

Site Boundary - Means a line within which the land is owned, leased, or otherwise controlled by the licensee. The site boundary for liquid releases of radioactive material is defined in Figure 3.8.1.

The site boundary for gaseous releases of radioactive material is defined in 3F Figure 3.8.2.

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AO.

Unrestricted Areas - Means any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals f rom exposure to radiation r*

and radioactive materials or any area within the site boundary used for residential quarters or

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initustrial, commercial, institutional and/or recreational purposes.

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Reportable Event - A Reportable Event shall be any plant occurrence or event which must be reported, per 10 CFR 50.73, requiring written reports to the Commission.

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Dose 2.

Dose a.

The dose or dose commitment to an individual a.

Cumulative dose contributions for the current A

from radioactive materials in liquid effluenta calendar quarter and year from liquid effluents released from the site (Figure 3.8.1) shall be shall be determined in accordance with the ODCM timited:

monthly.

l 1.

During any calendar quarter to 11.5 aren j

to the total body and to

-<5 mrem to any organ, and r

2.

During any calendar year to 13 mrem to the total body and to 110 mrem to any organ, b.

Ulth the calculated dose from the release of radioactive materials in 11guld ef fluents exceeding any of the above limits, within 30 days submit to the Commission a special report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits. This' special report shall also include (1) the results of radiological analyses j

of the drinking water source, and (2) the radio-logical impact on finished drinking water supplies with regard to th*e requirements of 40CFR141, Safe 27 Drinking Water Act.

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3.0 LIMITING CONDITIONS FOR 44PERATION 4.0 SURVEILLANCE REQUIREMENTS 3.

Liquid Radwaste System 3.

Liquid Radwaste System a.

Doses due to liquid releases shall be pro-a.

The liquid radwaste treatment system shall be used used to reduce the radioactive materials in liquid jected at least once each month in accordance wastes prior to their discharge when the projected with the ODCM.

doses due to the liquid ef fluent from the site (Figure 3.8.1) when averaged over one month would exceed 0.06 mrem to the total body or 0.2 mrem to any organ, b.

With radioactive liquid waste being discharged without treatment in excess of the limit in (a) above, within 30 days submit to the Commission a special report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) to be taken to restore equipment to operable status, and 3.

Summary description of action (s) taken to prevent a recurrence.

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2.

Dose fro.

2 Cases

2. Dose from Nobel Cases

a. The air dose due to noble gases released in gaseous

a. Cumulative dose contributions for the current effluents from the site (Figure 3.8.2) shall calendar quarter and year from nobel gases in be limited to the folicain values:

gaseous effluents shall be determined in accord-ance with the ODCM monthly.

1. During any calendar quarter, to fj5 stad for gamma radiation and 110 mrad for beta radiation, and

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2. During any calendar year, to 110 mrad for gamma radiation and 1:20 mrad for beta radiation.

b. With the calculated air doce from radioactive noble gases in gaseous ef fluent exceeding any of the above limits, within 30 days submit to the Commission a special report which identifies the cause(s) for exceeding the limits (s) and defines the corrective, actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.

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3.0 1.It11 TING CONDITIONS FOR OPERATION 4.0 SURVEII. LANCE REQUIREMENTS

3. Dose from I-131, tritium, and radioactive particulates

3. Dose from I-131, tritium, and radioactive particulates with half-lives greater than eight days.

with half-lives greater than eight days,

a. The dose to any organ of an individual due to

a. Cumulative dose contributions for the current calendar I-131, tritium, and radioactive particulates quarter and year from I-131, tritium, and radioactive with half-lives greater than eight days released particulates with half-lives greater than eight days in from the site (Figure 3.8. 2) in gaseous ef fluent gaseous ef fluents shall be determined in accordance witl shall be limited to the following:

the ODCM monthly.

1.

During any calendar quarter to <7.5 mrem, and 2.

During any calendar vear to <l5 mrem.

h. With the calculated dose from the release of 1-131, tritium, and radioactive particulates with half-lives greater than eight days exceeding any of the above limits, within 30 days submit to the Commission a special report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.

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e 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

4. Offgas Treatment System

4. Offgas Treatment System

a. The offgas treatment system shall be in a.

Following each isotopic analysis of a sample of operation whenever the main condenser air gases from the steam jet air ejector required by ejector system is in operation. Components 4.8.B.S.c, verify that the maximum storage tank of the system shall be operated to provide activity limit specified in 3.8.B.4.e cannot be the maximum holdup time obtainable except exceeded using the method in the ODCM.

during periods of equipment maintenance.

h. With gaseous waste being discharged for more than 7 days with a holdup time of less than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, within 30 days submit to the Commission a special report which includes the following information:

1.

Identification of equipment or sub-systems not functional and the reason.

2.

Action (s) taken to restore equipment to functional status.

3.

Summary description of action (s) taken to prevent a recurrence.

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D.

Dose from All Uranium Fuel Cycle Sources D. Dose from All Uranium Fuel Cycle Sources

1. The dose or dose commitment to any member

1. Cumulative dose contributions from all liquid and of the general public from all uranium gaseous effluents shall be determined in fuel cycle sources is limited to 125 mrem accordance with Specifications 4.8.A.2.a.

to the total body or any organ (except for 4.8.B.2.a, and 4.8.B.3.a and in accordance with the thyroid, which is limited to 175 mrem) the ODCM.

over a period of 12 consecutive months.

2. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.8.A.2.a.1, 3.8.A.2.a.2, 3.8. B. 2.a.1,

3. 8. B. 2.a. 2, 3. 8. B. 3.a.1, o r 3.8.B.3.a.2, prepare and submit within 30 days a special report to the Commission which defines corrective actions and cal-culates the highest radiation exposure to any member of the general public from all uranium fuct cycle sources (including all effluent pathways and direct radiation).

Unless this report shows that exposures a re less than the 40 CFR Part 190 standard, either apply to the Commission for a variance to continue releases which exceed the 40 CFR Pa r t 190 stand'ard or reduce subsequent releases 3f to permit the standard to be met.

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.13 FIRE DETECTION AND PROTECTION SYSTEMS 4.13 FIRE DETECTION AND PROTECTION SYSTEMS Applicability:

Applicability:

Applies to instrumentation and plant systems used for applies to the periodic testing of instru-fire detection and protection of the nuclear safety-mentation and plant systems used for fire related structures, systems, and components of the plant detection and protection of the nuclear safety related structures, systems, and Obj ect ive:

compon ~ ats.

To insure that the structures, systems, and components Objective:

of the plant important to nuclear safety are protected from fire damage.

To verify the operability of instrumentation and plant systems used for fire detection and Specification:

protection of nuclear safety related structures, systems, and components.

A. Fire Detection Instrumentation Specification:

1. Except as specified below, the minimum fire detection instrumentation for each fire A. Fire Detection Instrumentation detection zone shown in Table 3.13.1 shall he operable whenever equipment in that 1.

Fire detection instrumentation in each of fire detection zone is required to be the zones in Table 3.13.1 shall be demon-4 o pe rable,

strated operable every six months by performance of functional tests.

2. If specification 3.13.A.1 cannot be met, within one hour establish a fire watch patrol to inspect 2.

Alarm circuity associated with the fire the zone (s) with inoperable instruments at least detector instruments in each of the zones 37 once per hour. Restore the minimum number of in Table 3.13.1 shall be demonstrated instruments to operable status within 14 days or operable every six months.

EI submit a special report to the Commission within l

30 days outlining the cause of the inoperability and the plans and schedule for restoring the 57 instruments to operable status.

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3.0 Lill1TlHG CONDITIONS F0lt OPERATION 4.0 SURVEILLANCE REQUIREHENTS

2. With one of the pumps required by Specification

e. Every three months verify that a 3.13.n.l.a inoperable, perform the Surveillance sample of fuel from the diesel oil required by Specification 4.13.R.2 and restore storage tank, obtained in accordance the inoperable pump to operable status within with ASTH-D270-65, is within the seven days or provide a special report to the acceptable limits specified in Commission within 30 days outlining the plans Table 1 of ASTil.D975-74 when checked and procedures to be used to provide for the for viscosity, water, and sediment.

loss of redundancy in the Fire Suppression Water system.

3. With the fire suppression water system other-

f. Every 18 months subject the diesel-vise inoperable:

driven fire pump engine to an inspection

.in accordance with procedures prepared

a. Establish a backup fire Suppression Water In conjunction with the manufacturer's System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, recommendations for this class of standby service.

b. provide a special report to the Commission within 14 days outlining the actions taken

g. A simulated automatic actuation of and the plans and schedule for restoring the each fire pump and the screen wash / fire system to operable status, pump, including verification of pump capability, shall be conducted every 18 months.

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h. The yard main and the reactor building and 2f turbine building headers shall be flushed every 12 months.

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1. System flow tests shall be performed ro every-three years.

5E J. Valves in flow paths supplying fire 24 suppression water to safety related structures, systems, and component shall be cycled every 12 months.

3.13/4.13 225 i

p 3.0 1.lMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

2. If Specification 3.13.C.1 cannot be met, within one hour hoses supplied from operable hose stations shall be made available for routing to each area with an inoperable hose station. Restore the inoperable hose station (s) to Operable D. Yard Hydrant Hose Houses status within 14 days or submit a special report to the commission within 30 days

1. The yard hydrant hose houses listed in outlining the cause of the inoperability Specification 3.13.D.1 shall be demon-and the plans and schedule for restoring strated operable as follows:

the system to Operable status.

a. Each month a visual inspection D. Yard Ilydrant Hose Houses shall be conducted of the yard hydrant hose houses to assure all

1. Whenever equipment in the following buildings-required equipsent is available.

is required to be operable, the yard hydrant hose houses in the main yard loop adjacent

b. Every six months (in the spring and to those building shall be operable:

fall) visually inspect each yard fire hydrant and verify that the

a. Diesel Generator Building hydrant barrel is dry and that

b. Turbine Building the hydrant is not damaged.

c. Screenhouse

d. Reactor Building

c. Every year conduct a hose hydrostatic

e. Administration Building test at a pressure at least 50 psig i

greater than the maximum pressure

2. If Specification 3.13.D.1 cannot be met, available at any yard hydrant hose within one hour have sufficient additional house and conduct an inspection of lengths of 2-in*ch diameter hose located all gaskets in the couplings. All jf adjacent operable yard hydrant hose degraded gaskets shall be replaced.

house (s) to provide service to the unpro-Cf tected area (s).

Restore the yard hydrant hose house (s) to Operable status within 14 r0 days or submit a special report to the if Commission within 30 days outlining the cause of tae inoperability and the plans

[d and schedule for restoring the system to g;

Operable status.

3.13/4.13 227

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS E. Sprinkler Systems E. Sprinkler Systems

1. The following spray or sprinkler systems

1. Each of the spray or sprinkler systems shall be operable whenever equipment in the listed in specification 3.13.E.1 shall protected area (s) is required to be operable:

he demonstrated operable as follows:

a. Diesel Generator and Day Tank Rooms

a. Each valve (manual, power operated,

b. Luhe Oil Drum Storage or automatic) in the flow path that

c. Tube 011 Storage Tank Sprinkler is not electrically supervised, locked,

d. Ilydrogen Seal Oil Unit Sprinkler scaled or otherwise secured in position, c.

Inhe 011 Piping System Sprinkler shall be verified to be in its correct

f. Lube 011 Reservoir position every month,

g. Itecirc HG Set Sprinklers i

h.

Intake Structure

b. Cycle each testable valve in the flow

2. If Specification 3.13.E.1 cannot be met, i

path through at least one complete within one hour establish a continuous fire cycle of full travel once each year.

watch with backup fire suppression equipment for the unprotected area (s).

Restore the

c. Perform a system functional test every syptem to operable status within 14 days or 18 months which includes, where appli-submit a special report to the Commission cable, simulated automatic actuation within 30 days outlining the cause of the of the system and verification that the inoperability and the plans and schedule automatic valves in the flow path for restoring the system to operable status, actuate,to their correct positions on a test signal.

d. At least once per 5 years by performing an air flow test through each open head sprinkler g7 header and verifying each open head sprinkler g

is unobstructed.

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e. At least once per 18 months by a visual r+

examination of system piping and sprinkler

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heads. An air flow test shall be performed

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upon evidence of obstruction of any open

]w head sprinkler.

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3.0 LlH1THIC COIIDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS F. Ita lon Systems F. Halon Systems l

1. The cable spreading room Italon system shall

1. The cable spreading room Halon system i

be operable with the storage tanks having shall be demonstrated operable as at least 95% of full charge weight and 90% of follows:

fulI charge prossure.

a. Each valve (manual, power operated, or l

2. If specification 3.13.F.1 cannot be met, automatic) in the flow path that is not within one hour establish a continuous fire electrically supervised, locked, scaled watch with backup fire suppression equipment or otherwise secured in position, shall in' the cable spreading room.

Restore the be verified to be in its correct position system to operable status within 14 days every month.

or submit a special report to the Commission within 30 days outlining the cause of the

b. Verify llalon storage tank weight and inoperability and the plans and schedule pressure *every six months, for restoring the system to operable status.

c. Perform a system functional test G. Penetration Fire Barriers every 18 months which includes veri-fying the system, including associated

1. All penetration fire barriers in fire area ventilation dampers, actuates manually houndaries protecting safe shutdown equipment and automatically, upon receipt of a shall be operable.

test signal.

2. If Specification 3.13.G.1 cannot be met,

d. Perform an air flow test every 3 years a continuous fire watch shall be through headers and nozzles to assure established on at least one side of the no blockage.

affected penetration (s) within one hour.

Restore the inoperable penetration fire

e. Visually examine headers and nozzles every barriers to Operable status within 14 days or 18 months. An air flow test shall be per-submit a special report to the Commission formed upon evidence of obstruction of any 37 within 30 days outlining the cause of the llalon system nozzle.

inoperability and the plans and Sf schedule for restoring the barriers to G. Penetration Fire Barriers Operable status,

l. A visual inspection of penetration fire barriers c'

@i in the fire area boundaries protecting safe shutdown equipment shall be conducted every ld 18 months, a

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2. Following repair or maintenance of a penetration fire barrier a visual inspection of the seal 3.13/4.13 shall be conducted.

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e 3.0 1.IMITING CONDITIONS FOR OPERATION 4.0 SURVEII. LANCE REQUIREMENTS 3.

Deviations are permitted from the required sampling schedule if samples are unobtainable due to hazardous conditions, seasonable unavaila-bility, or to malfunction of automatic sampling equipment.

If the latter occurs, every effort shall be made to complete corrective action prior to the end of the next sampling period.

4.

With the level of radioactivity-in an environ-2 mental sampling medium exceeding the reporting levels of Table 4.16.3 when averaged over any calendar quarter, submit a special report to the Commission within 30 days from the end of the affected calendar quarter pursuant to Specification 6.7.C.3.

When more than one of the radionuclides in Table 4.16.3 are detected in the sampling medium, this report shall be submitted ift concentration (1) concentration (2) +...

>l.0 limit level (1) limit level (2)

When ra'dionuclides other than those in Table 4.16.3 are detected and are the result of plant ef fluents, this report shall be submitted if the potential annual done to an individual,is equal to or greater gp than the calendar year limits of Specifications 3.8.A.2, 3.8.B.2, or 3.8.B.3.

This report is not m

El required if the measured level of radioactivity was not the result of plant effluents; however, in such l$

an event, the.:ondition shall be reported and described in the Annual Radiation Environmental Monitoring Report.

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IlllittIUH Silli r CitEW Coffr0SITION (liote 1) i e

APPI.lCAllt.E Pl. ANT CONDITIONS SilllTDOWN OR REFUEI.ING STAl TUP Olt Ruti !! ODE (Ilote 4:

CATECORY HODE AND

<212*F OR

>212*F 6 I (Note 2) 2 (flote 3)

No, l.icensed Senior Operators (I.50) 2 4

Total No. I.icensed Operators (I.SO& I.0) 6 3

Total flo. 1.icensed and Unlicensed Operators 1

0, Shift Technical Advisor Notes:

less than the minimum regiskrements for a period of time riot

1. Shift crew composition may be one to exceed two hours in order to accommodate an unexpected absence of one duty shift cree member provided immediate action is taken to restore the shift crew compositien'to within the minimum requirements specified.

include the licensed Senior Reactor Operator, or Senior Reactor Operator I. limited i

2. Does not to Fuel llandling, supervising alterations of the reactor core.

3. One 1.50 shall be in the control room or the shift supervisor's office at all times when p

the reactor is in the Startup or Run Hode or reactor coolant temperature is greater than or equal to 212*F.

At least 50% of the time, an 1.50 shall actually be in the control room

- m i 5 M

proper when the reactor is in the Startup or Run flode or reactor coolant teinperature is greater 5

than or equal to 212*F. -

4. Except for momentary switching to Startup Mode for testing.

236 6.1 4

6.2 Review and Audit Organizational units for the review and audit of facility operations shall be constituted and have the responsiht11 ties and authorities outlined below:

A. Safety Audit Committee (SAC)

The Safety Audit Committee provides the independent review of plant operations from a nuclear safety standpoint. Audits of plant operation are conducted under the cognizance of the SAC.

l

1. Membership

a. The SAC shall consist of at least five (5) persons.

h. The SAC Chairman shall be an NSP representative, not having line responsibility for operation of the plant, appointed by the Vice President, Nuclear Generation. Other members shall be appointed by the Vice President, Nuclear Generation or by such other person as he may designate. 1he Chairman shall appoint a Vice Chairman from the SAC membership to act in his absence.

c. No more than two members of the SAC shall be from groups holding line responsibility for operation of the plant.

d. A SAC member may appoint an alternate to serve in his absence, with concurrence of the Chairman.

No more than one alternate shall serve on the SAC at any one time. The alternate member shall have voting rights.

2. Qualifications

a. The SAC members should collectively have the capability required to review activities in the following areas:

nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, instrumentation and control, radiological safety, mechanical and electrical engineering, quality assurance practices, and other

[7 appropriate fields associated with the unique characteristics of the nuclear power plant.

o 5

s.

!d 6.2 237 M

f.

Investigstion of all Reportable Events and Events requiring Special Raports to the Commission.

g.

Revisions to the Facility Emergency Plan, the Facility Security Plan, and the Fire Protection Program.

h.

Operations Committee minutes to determine if matters considered by that Committee involve unreviewed or unresolved safety questions.

1.

Other nuclear safety matters referred to the SAC by the Operations Committee, plant management or company management.

J.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

k.

Repotts of special inspections and audits conducted in accordance with specification 6.3.

1.

Changes to the Of faite Dose Calculation Manual (ODCM).

l m.

Review of investigative reports of unplanned releases of radioactive material to the environs.

6.

Audit - The operation of the nuclear power plant shall be audited formally under the cognizance of the SAC to i

assure saf e facility operation.

a.

Audits of selected aspects of plant operation, as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be performed with a frequency commensurate with their nuclear safety significance and in a manner to assure that an audit, of all nuclear safety-related activities is completed within a period of two years. The audits shall be performed in accordance with appropriate written instructions and procedures.

h.

Audits of aspects of plant radioactive effluent treatment and radiological environmental monitoring -shall be performed as follows:

4 1.

Implementation of the Offsite Dose Calculation Manual and quality controls for ef fluent monitoring at l

1 east once every two years.

2.

Implementation of the Process Control Program for solidification of radioactive waste at least once every l

two years.

3.

The Radiological Environmental Monitoring Progran and the results thereof, including quality controls, at l

least once every year, i

l ff c.

Periodic review of the audit program should be performed by the SAC at least twice a year to assure its g,

adequacy.

ao

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3 d.

Written reports of the audits shall be reviewed by the Vice President Nuclear Generation, by the SAC g

at a scheduled meeting, and by members of Management having responsibility in the areas audited.

P r

6.2 239 tn o) i

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7. Authority The SAC shall be advisory to the Vice Presicent, Nuclear Cencration.

8. Records Hinutes shall be prepared und retained for all scheduled meetings of the Safety Audit l

Committee. The minutes shall be distributed within one month of the meeting to the Vice President, Nuclear Generation, the General Manager Nuclear Plants, each member of the SAC, and others designated by the Chairman or Vice Chairman, There shall be a formal approval of the minutes.

9. Procedures A written charter for the SAC shall be prepared that contains:

a. Subjects within the purview of the group.

b. Responsibility and authority of the group.

c. Mechanisms for convening meetings.

d. Provisions of use of specialists or subgroups.

c. Authority to obtain access to the nuclear power plant operating record files and operating personnel when assigned audit functions.

f. Requirements for distribution of reports and minutes prepared by the group to

+

3" others in the NSP Organization.

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P 6.2 240 w.

l

f. Investigation of all Reportable Events and Events requiring Special Reports to the Commission.

g. Drills on emergency procedures (including plant evacuation) and adequacy of communication with off-site

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support groups.

h. All procedures required by these Technical Specifications, including implementing procedures,of the Emergency Plan and the Security Plan (except as exempted in Section 6.5.F), shall he reviewed with a frequency commensurate with their safety significance but at an interval of not more than two years,

i. Perform special reviews and Investigations, as requented by the Safety Audit Committee.

J. Review of investigative reports of unplanned releases of radioactive materini to the environs.

k. All changes to the Process Control Program (PCP) and the Offsite Dose Calculation llanual (ODCll).

S. Authority In the event of disagreement between the recommendations of the The DC Shall be advisory to the Plant !!anager.

the course determined by the Plant llanager to be the more conservative will be A written summary of the disagreement will be sent to the Vice President, !!uclear Generation and the l OC and the Plant !!anager, followed.

Chairman of the SAC for review.

6. Records tilnutes shall be recorded for all meetings of t.he OC and shall identify all documentary material reviewed.

The minutes shall be distributed to each member of the OC, the Chairman and each member of the Safety Audit fluclear Generation and others designated by OC Chairman or Vice Chairman.

Committee, the Vice President, N

7. Procedures g

5 A written charter for the OC shall be prepared that contains:

m "o

Responsibility and authority of the group.

a.

Content and method of submission of presentations to the Operations Committee.

w b.

242 6.2

r B.

Reportable Events "h

The following actions shall be taken for Reportable Events:

a.

The Commission shall be notified by 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 Operations Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.

N 2e Z

b g

6.7 250

C.

Environmental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional Office or designate:

1.

Annual Radiation Environmental Monitoring Report

a. Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.

h. The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use consensus required by Specification 4.16.B.I.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

c. The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of. Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

d. The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the reactor; and the results of Ifcensee participation in the -

l[

Interlaboratory Comparison program, required by Specification 4.16.C.I.

E.

5 251 6.7 I

2. Environmental Special Reports Uhen radioactivity levels in samples exceed limits specified in Table 4.16.3 an Environmental Special Report shall be submitted within 30 days from the end of the affected calendar quarter.

For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period.

In these cases the potential for exceeding the quarterly limits will be reported within the 30 day i

period to be followed by the Environmental Special Report as soon as practicable.

l

3. Other Environmental Reports (non-radfological, non-aquatic)

Written reports for the following items shall be submitted to the appropriate NRC Regional Administrator:

a. Environmental events that Indicate or could result in a significant esivironmental impact causally related to plant operation. The following are examples: excessive bird impac-tion; onsite plant or animal disease outbreaks; unusual mortality of any species protected by Endangered Species Act of 1973; increase in nuisance organisms or conditions; or excessive environmental Impact caused by herbicide application to transmission corridors associated with the plant. This report shall be submitted within 30 days of the event and shall (a) descrlhe, analyze, and evaluate the event, including extent and magnitude of the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) Indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (c) indicate the agencies notified and their preliminary responses.

b. Proposed changes, tests or experiments which may result in a significant increase in any,

adverse environmental impact which was not previously reviewed or evaluated in the Final Environmental Statement or supplements thereto. This report shall include,an evaluation to the cevironmental impact of the proposed activity and shall be submitted 30 days prior to implementing the proposed change, test or experiment.

Eg D. Syecial Reports s

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Unless otherufse Indicated, special reports reqnfred by the Technical Specification shall be submitted f

to the appropriate NRC Regional Administrator within the time period specified for each report.

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6.7/6.8 752 l;

c.

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6.8 EllVIRON!!ENTAT. QllAl.IFICATIOli A. By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors "Guldelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in operating Reactors" (DOR Cuide11nes); or, NUREC-0588 " Interim Staff Position on Environmental qualification of Safety-Related Electrical Equipment", December 1979. Copies of these documents are attached to Order for

!!odification of License DPR-22 dated October 24, 1980 B. By no later than December 1, 1980, complete and auditfble records must be available and maintained I

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 compilance with the DDR Cuidelines or NUREG-0588. Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further quallfled.

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