ML19339B529

Amends 74 & 73 to Licenses DPR-44 & DPR-56,respectively, Revising Tech Specs to Incorporate Certain TMI-2 Lessons Learned Category a Requirements

ML19339B529
Person / Time
Site:	Peach Bottom
Issue date:	10/28/1980
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19339B530	List: ML19339B529 ML19339B534
References
NUDOCS 8011070130
Download: ML19339B529 (23)

Text

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UNITED STATEc 8-

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NUCLEAR REGULATORY COMMISSION g

. ASHINGTON, D. C. 20603 W

y PHILADELPHIA ELECTRIC C0WANY j#

PUBLIC SERVICE ELECTRIC AND GAS COWANY DELMARVA POWER AND LIGHT COWANY ATLANTIC CITY ELECTRIC COWANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No; DPR 44 1.

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

A.

The application-for amendment by Philadelphia Electric Company, et al. (the licensee) dated September 15, 1980, complies with the standards and requirements of _:..: Atomic Energy Act of 1954, as amended (the Act), and the Connission'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.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to tht, license amendment and paragraph 2.C.(2)of Facility Operating License No. DPR 44 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and

-B. as revised through Amendme'nt No. 74, are hereby incorporated ir the license'.

PEC0 shall operate the facility in accordance with the Technical. Specifications.

i 8011070 l.30

~ 2-3.

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

FOR THE NUCLEAR REGULATORY COPNISSION uJh tl.

Robert W. Reid, Chief

~

Operating Reatiors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 28, 1980 t

/

Q l

W

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4 ATTACHMENT TO LICENSE AMENDMENT NO.74 FACILITY OPERATING LICENSE N0. DPR-44

-DOCKET NO. 50-277 n.

' i Replace the following pages of the Appendix "A" Technical

' Specifications with the-enclosed pages. The revised.pages-

~

are ioentified by amendment number and contain vertical lines indicating the area of change. : Page 85.was.not changed; it is included for convenience only.

Insert Page Remove Page.

iii iii' 77 77 78 78 85 85 86 86 245 245 246 246 263 (new page) n L

'I i

1

~

PBAPS TABLE 0,F CONTENTS' (cont'd)

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIR EMENTS PAGE NO.

i 3.14 FIRE PROTECTION 4.14 240c

'A.

Water Fire ' Protection ~ System A

240c B.

CO2 Fire Protection System

.B 240g C.

Fire Detection C

2401 D.-

Fire Barrier Penetrations D

240j 5.O MMOR DESIGN FEATURES 241 6.0 ADMINIS M TIVE CONTROLS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246

6. 5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety. Limit violation 253

6. 8 Procedures 253 6.9 Reporting Requirenents 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 -

6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 1

1 1

4 s

Amendment No.

Jf 74

-lii-

TABLE 3.2.F d

SURVEILLANCE INSTRUMENTATION e

Ft a

Minimum No.

,e of Operable Type Instrument Indication Channels

. Instrument and Range Action E'

l 2

Reactor Water Level

. Recorder 0-60" (6) (7)

Indicator 0-60" 2

Reactor Pressure Recorder 0-1500 psig (1) (2) (3)

Indicator 0-1200 psig

'2 Drywell Pressure Recorder 0-70 psig (1) (2) (3) 2 Drywell Temperature Recorder 0-4000T (1) (2) (i) 0 Indicator 0-400 F 4_

0 2

Suppression Chamber Water Recorder 0-600 F (1) (2) (3)

Indicator 0-400"F Temperature 2

Suppression Chamber Water Recorder 0-2 ft.

(1) (5)-

Level Indicator 0-2 ft.

1

. Control Rod Position 28 Volt Indicating

)

Lights

)

)

(1) (2) (3) (4 )-

1 Neutron Monitoring SRM, IRM, LPRM

)

0-100%

)

1

. Safety-Relief Valve

. Acoustic or (8)

Position Indication thermocouple

PBAPS NOTES FOR TABLE 3.2.F I

1)~

From and after the date that one of these parameters is j

reduced to one-indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

2)

From and after the date that one of these parameters.is-not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

3)

If the requirements of notes (1) and (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4)

These surveillance instruments are considered to be redundant to each other.

5)

In the event that all indications of this parameter are disabled and such indication cannot be restored in six-(6) hours, an orderly shutdown shall be initiated and

~

the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.

6)

' With.the number of operable channels less than the minimum number of instrumentation channels shown in Table 3.2.F, either restore the inoperable channel to an operable status within 7 days, or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1 I

7)

If this parameter is not indicated in the control room, either restore at least one inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

8)

If this parameter is not indicated in the control room, either restore at least one channel to operable status I

within thirty' days or be in at least hot shutdown within the'next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. M 74. -

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1 TABLE 4.2.E 1

' MINIMUM TEST AND CALIBRATION FREQUENCY FOR DRYWELL LEAK DETECTION Instrument Channel Instrument Functional Calibration. - Instrument' Test Frequency Check

~1)

Equipment Drain Sump Flow Integrator (1)

Once/3 months

'Once/ day 2)

Floor Drain Sump Flow Integrator (1)

Once/3' months Once/ day (1)

Once/3 months once/ day

'3)

Air Sampling-System a

4-m-

T

j 9

. 0 e

O

9 TABLE 4.2.F UNITJ2 h.

e.

HINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION' E.-

Instrunent Channel-Calibration Frequency I:sstrument Check.

.5

1) LReactor. Level Once/ operating cycle Once Each' Shift z,

2)

Reactor' Pressure

'Once/6 months Once Each' Shift 3)

Dryuell Pressure-Once/6 months Ionce Cach Shift u.

..4)

Dryuell Teuperature Once/6 inonths Once Each Shift

5). Suppression Chamber Tennperature once/6 months-Once Each Shift-

6 )

Suppression Chainber Water Level once/6 months Once EacifShift

'7)

Control Rod Position NA O n'c e Each Shift 8)

Neutron lionitoring (APRS)

Twice Per Ucek once Each Shift

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on 9)

Safety / Relief-Valve Position Once/ operating cycle Onc e / month Indicator (acoustics)

I

10) Safety / Relief Valve Position NA*

Once/ month Indicatcr (thermocouple)

11) Safety Valve _ Position once/ operating cycle Once/ month Indica tor facoustics)

12) Safety Valve Position-NA*

Once/ month Indicator (thernocouple)

• Perforn instrunent functional check:once per operating cycle

TABLE 4.2.F UNIT 2.

j MINI!!Ulf TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION es -

' E. -

. Instrument Channel Calibration Frequency

. Instrument Check

' s

.3.

1 )-

Reactor ~ Level once/ operating cycle Once-Each Shift

. x :2)

Reactor Pressure' Once/6 months once Each ShifC

.3)

DrywellJPressure once/6 months

.Once Each Shift' N

4)- Drywell Teuperature Once/6 months 0nce Each Shift

~

5)

Suppression Chamber Temperature once/6 months Core Each Shift 6)

Suppression Chamber Water Level Once/6 months

'Once Each Shift ~

-7 ) ' Control Rod Position HA Once-Each Shift.

.8 )

Neutron.!!onitoring (APRN)

Twice Per Ucek Once Each Shift o>.

. 9 )'

Safety / Relief 'Valve Position Onc e / operating c 'le Once /aonth

~ *

~1ndicator (acoustics)

- s

10) SafetyfMelief Valve Position NA*

Once/uonth Indicator (thermocouple)

11) Safety Valve Position-Once/ operating cycle Once/ month Indica t or (acoustics)

12) Safety Valve Position UA*

Once/ month Indicator (thernocouple) 4

• Perform instrunent functional check once per operating cycle e

b 4

+

Superintendent SIO* #

1 3

Asst. Superintendent SID*

a I

h l

l l

k Operations Engineer (SID)

• Clerical EngineerTechnical(SLO)

Engineer Maintenance f

' Security Force

" Engineer Reactor

% intenance

- Engineer I & C (and/or Rseults) h

= Engineer Health Physics

" Custodial l)

- Engineer Chectistry

= Stores 1/S Shift Supt. (SIC)**

~ Engineers

~

- --1/S Shift Technical Advisor ***

~

/S shift Supr. (SID)**

1 1/S Control Op. Nuclear (ID)

- At least one of these shall be licensed.

2/S Asst. Cont. Op. Nuclear (LO)

Only one of these need to be licensed during a training and qualification 1/S Plant Op.

Period provided a second SID is available on site.

1/S Asst. Plant Op.

X/S-Number of men per shift. All shift 5

1/S Aux. Op.

Positions are marked.

ID NRC Licensed Operator SID - NRC Licensed Senior Operntor Responsible for onsite fire protection activities

• • • - Not applicable with plant in the shutdown or refuel ORGANIZATION P3R CONDUCT OF mode.

PLANP OPERATIONS Figure 6.2-2

D*FD *]D))Y ob Ju o

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4 PBAPS 6.3 Facility Staff Qualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI NIG.1-1971 for comparable positions, except for (1) the Engineer-

!!ealth Physics who shall meet or exceed the qualifications of Regulatory Guide 1.3, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 Training 5.4.1 A retraining and replacement training prograu for the facility staff shall be maintained under the direction of the Station Superintendent and shall meet the requirements of Section 5.5 of ANSI :i,13.1-1971 and 10 CFR 55, Appendix A.

6.4.2 A training program for the Fire 3rigado shall be conducted such that Fire Brigade uembers couplete an instruction program within a tuo year period.

Regularly planned meetings will be held every 3 aonths.

6.5 Review and Audit 6.5.1 Plant Operation Review Commitcee (PonC)

Function 6.5.1.1 The Plant Operation Review Comuittoc shall function to advise the Station Superintendent on all matters related to nuclear safety.

Composition 6.5.1.2 The Plant Operation Review Committoo shall be coaposed of the:

Station Superintendent-Chairman Station Assistant Superintendent Engineer - Technical Engineer - if aintenance Engineer - Operations Engineer - Results Engineer - Reactor Engineer - Instrument 6 Control Enginee r - IIealth Physics Engineer - Che*11stry Shift Superintenden' Alternates 6.5.1.3 Alternate nenbers shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in t' ORC activities at any one time.

Amendment No. )f. M % 74

-246-

P3APS 6 ~.14 Integrity of Systems outside Containnant The. licensee shall implement a program to reduce leakage from systema outside containment that would or e

could.contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

This program shall include the following; 1)

P.gvisions establishing preventive maintenance and pericdic visual inspection requirements, and 2)

System leak test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals.

The systems subject to this testing are (1) Residual lleat Removal, (2) Core ~ Spray, (3) Reactor Water Cleanup,-(4) IIP C I, and (5) RCIC.

6.15-Iodine Monitorina The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

• under accident conditions.

This program shall include the following:

1.

Training of personnel, 2,

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

Areas requiring personnel access for establishing hot shutdown condition.

Amendment No. 74

-263-

[pa at ou, o

UNITED STATES

['

g NUCLEAR REGULATORY COMMISSION

. r wAm W mn.o.caorss r

/

PHILADELPHIA ELECTRIC COWANY PUBLIC SERVICE ELECTRIC AND GAS COMPA E DELMARVA POWER AND LIGHT COWANY ATLANTIC CITY ELECTRIC CON ANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STAYION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.73 License No. DPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company, et al. (the licensee) oated September 15, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of tha public, and (ii) that such activities will be conducted in compitance 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.

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 73, are hereby incorporated in the license.

PEC0 shall operate the facility in accordince with the Technical Specifications.

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

3.

FOR THE NUCLEAR REGULATORY COMISSION 1

/

Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 28, 1980 G

).

I

' ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE NO.'DPR-56 DOCKET NO. 50-278 Heplace 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 area of change. Page 85 was not changed; 3

it is included for convenience only.

t Remove Page Insert Page 111 iii 77 77 78 78 85 85-86 86 245 24 5 -

246 246 263 (new page) v i

~

PBAPS TABLE OF CONTENTS' (cont'd)

SURVEIIIANCE LIMITING CONDITIONS FOR OPERATION REQUIR EMENTS PAGE NO.

3.14 FIRE PROTECTION 4.14 240c A.

Water Fire Protection System A

240c 4

B.

CO2 Fire Protection System B

240g C.

Fire Detection C

2401 D.

Fire Barrier Penetrations D

240j,

S.0 MA70R DESIGN FEATURES 241 6.0 ADMINISMATIVE CONTROLS 243 l

6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246

{

6. 5 Review and Audit 246 s

6.6 Reportable Occurrence Action 253 6.7 Safety Limit violation 253 3

6. 8 Procedures 253 6.9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 -

6.13 High Radiation Area 262 6.14 Integrity' of Systems Outside Containmen't 263 6.15 Iodine Monitoring 263 6.16 Enviioriiental Qualification 264 I

i l

.i Amendment No. g g 73

_111_

W -

TABLE 3.2.F

(

SURVEILLANCE INSTRUMENTATION E'

2

.[

Minimum No.

,0 of. Operable Type

-Instrument Indication Channels Instrument and Range Action U-2 Reactor Water Lesel.

Recorder 0-60" (6) (7)

Indicator 0-60" 2

Reactor Pressure Recorder 0-1500 psig (1) (2) (3)

Indicator 0-1200 psig 2

Drywell Pressure Recorder 0-70 psig (1) (2) (3) 2 Drywell Temperature' Recorder 0-4000T (1) (2) (3) 0 Indicator 0-400 F 0

2 Suppression Chamber Water Recorder 0-600 F (1) (2) (3)

Temperature Indicator 0-400 F 2

Suppression Chamber Water Recorder 0-2 ft.

(1) (5)

Level Indicator 0-2 ft.

1 Control Rod Position 28 Volt Indicating

)

Lights

)

)

(1) (2) (3) (4) 1 Neutron Monitoring SRM, IRM, LPRM

)

0-100%

)

1 Safety-Relief Valve Acoustic or (8)

Position Indication thermocouple

PBAPS NOTES FOR TABLE 3.2.F 1)

From and after the date that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding thirty days unless such instrumentation is sooner made operable.

2)

From and after the date that one of these parameters is not indicated in the control _ room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

3)

If the requirements of notes (1) and (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4)

These surveillance instruments are considered to be redundant to each other.

5)

In the event that all indications of this parameter are disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall_be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours..

6)

With the number of operable channels less'than the minimum number of instrumentation channels shown in Table 3.2.F, either restore the inoperable channel to an operable status within 7 days, or be in at least hot shutdown within the next'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

7)

If this parameter is not indicated in the control room, either restore at least one inoperable channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

8)

If this parameter is not indicated in the control room, either restore at least one channel to operable status within thirty days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

f Amendment No.'40','73,

i

~

TABLE 4.2.E MINIMUM TEST AND CALIBRATIOF FREQUENCY FOR DRYWELL LEAK DETECTION Instrument Channel Instrument Functional Calibration.

Instrument-Test Frequency Chec's-1)

Equipment Drain Sump Flow Integrator (1)

Once/3 months Once/ day 2)' Floor Drain Sump Flow Integrator (1)

Once/3 months Once/ day-3)

-Air.' Sampling System

'(1)

Once/3 months-Once/ day E>

M e.

M' h.

i.

m U

u W

e

T Al:LE 4.2.F UNIT 3 E

I

!!INIllUH TEST AND CALIBRATIO!1 FREQUEllCY FOR SURVELLLANCE INSTRUMENTATION Instrument Channel Calibration Fruquency Instrument Check

~

1) **RcActor Level Once/ operating cycle Once Each: Shift I

• Reactor Level onec/6 uonths Once Each Shift

2) Reactor Pressure Once/6 menths Once Each Shift w

3)'Drywell Pressure once/6 months.

Once Each Shift 4). Drywell Temperature once/6 months once Each Shift.

5). Suppression Chamber Temperature once/6 uonths Once Each Shift

. Suppression Chamber Water Level once/6 months once Each Shift 6) 7)

Control Rod Position NA Once Each Shift 8)

Neut ron !!onitoring ( Af litt )

T91cc Per lleck once Each' Shift 9)

Safety /Helief Valve Position Gnce/ operating cycle Once/ month Indicator (acoustics)

10) Safety / Relief Valve Position NA***

Once/ month-Indicator (thermocouple)

11) Safety Valve Position Indicator Once/ operating cycle Once/uonth (acoustics)

12) Safety Valve Position Indicator 11A***

Once/ month (thermocouple)

Deleted when-undifications authorized by Auendusent.No. 67 are completed.

Effective when modifications authorized by Auendment No. 67 are completed.

Perform instrument functional check once per operating cycle.

Euperintendent SLOD #

Eg

/ mt. Superintendent SIO5 a

I o

e E

8 l

l OperationsEngineer(SIO)

" Clerical EngineerTechnical(SLO)

Engineer Maintenance

' Security Force

" Engineer Reactor

% intenance

- Engineer I & C (and/or Rssults)

= Engineer Health Physics

" Custodial

- Engineer Chemistry

= Stores y

1/S Shift Supt. (SLO)**

- Engineers

~

1/S Shift Technical Advisor *o*

' 1/S Shift Supr. (SIO)**

1/3 Control Op. Nuclear (LO)

A leas ne f ese a 1 be licensed.

2/S Aest. Cont. Op. Nuclear (IO)

Only one of these need to be licensed g

during a training and qualification 1/S Plaint Op.

peri d provided a second SLO is available on site.

1/S Aest. Plant Op.

l.

I/S-Number of men per shift. All shift 1/S Aux. Op.

positions are marked.

LO NRC Licensed Operator SLO - NRC Licensed Senior Operntor Responsible for onsite fire protection activities

• • • - Not applicable with plant in the shutdom or-refuel ORGANIZATION M R CONDUCT OF mode.

pLANP OPERATIONS Figure 6.2-2

D**D

• D 3Y 2 1

.m oc o

~PBAPS 6.3 Facility Staff Qualifications 6.3.1 Each member of the facility staff shall meet or c::c e e d.

the' minimum qualifications of_AUSI NLU.1-1971 for comparabl0 positions, except for (1) the, Engineer-

!!ealth Physics.who shall meet or' exceed the qualifications-of Regulatory Guide 1.3, September 1975 and (2).the Shift Technical Advisor who shall have a bachelor's degree or equivalent-in a scientific or engineering discipline with specific training in plant

' d e s.i gn,. a n d response and analysis of the plant for transients and accidents.

6.4 Training 5.4.1 A retraining and replacement training prograu for the facility staff shall be maintained under the direction of the Station Superintendent and shall nect the requirements of Section 5.5 of ANSI N13.1-1971 and 10 CFR 55, Appendix A.

6.4.2 A training program for the Fire 3rigade shall be conducted such:that Fire Erigade uember' couplete an instruction program within a tuo year period.

Regularly planned meetin,qs will be held every 3 aonths.

6.5 Review and Audit 6.5.1 Plant-Operation nevieu committee (PonC)

Function 6.5.1.1 The Plant Operation Review Comuittee shall function to advise the Station Superintendent on all matters related to nuclear safety.

4 Composition 6.5.1.2 The Plant Operation Review Committee shall be coaposcJ of the:

Station Superintendent-Chairman Station Assistant Superintendent Engineer - Technical Engineer - Itaintenance Engineer

. Operations Engineer - Results Engineer - Reactor Engineer - Instrument 4 Control Engineer - Ilealth Physics Engineer.- Chenistry Shift Superintendent Alternates 6. 5.~ 1. 3 Alternate nenbers shall be appointed in writing by the

.PORC Chairman to serve or a temporary basis; houever, no more-than two alternates shall participate in Pu2C j

cetivities at any one time.

l

. Amendment No.,?pI [ [ 73'

-246-

~

P3APS 6.14 Integrity of Systems outside Containment The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as pracrical levels.

This program shall include the following:

1)

Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2)

System leak. test requirements, to the extent permitted by system design and radiological conditions, for each system at a frequency not to exceed refueling cycle intervals.

The systems subject to this testing are (1) Residual lleat Removal, (2) Core Spray, (3) Reactor Water Cleanup, (4) IIP C I, and (5) RCIC.

6.15 Iodine !!onitoring The licensee shall implement a-program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

• under accident conditions.

This program shall include the following:

1.

Training of personnel, 2,

Procedures for monit ring, and 3.

Provisions for maintenance of sampling and analysis equipment.

Areas requiring personnel _ access for establishing hot shutdown condition, a

4

-263-Amendment No. 73

.