ML20137W145

Forwards marked-up Pages of 851125 Draft Tech Specs, Retaining Administrative Controls Re Fire Protection Program

ML20137W145
Person / Time
Site:	Perry
Issue date:	11/29/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 8512100180
Download: ML20137W145 (30)

Text

_

~

NOV 2 91985 Docket Nos. 50-440/441 DISTRIBUTION

Docket. File, JPartlow hRC PDR JStefano Local PDR EHylton fir. Murray E. Edelman BWR#4 Reading ACRS (10)

Vice President - Nuclear Group RBernero The Cleveland Electric Illuminating Company Woodhead, OELD P.O. Box 5000 EJordan Cleveland, Ohio 44101 BGrimes

SUBJECT:

FIRE PROTECTION PROGRAM FSAR/ TECHNICAL SPECIFICATION CHANGES FOR THE PERRY NUCLEAR POWER PLANT In your letter of November 15, 1985, you proposed to delete the fire protection progran elements from the Perry Unit 1 Technical Specifications, and in lieu thereof, to document those elenents in the FSAR. The staff finds this change, wherein you describe and control the fire protection program through the FSAR, to be acceptable, provided you retain the administrative controls related to the program as reflected in the enclosed markup pages of the November 12, 1985 final draft of the Technical Specifications. CEI is requested to certify the Perry, Unit 1 Technical Specifications implementing the changes reflected in the enclosure.

Should there be any questions or need to discuss this matter further with the staff, please let me know.

Sincerely, Original Signed by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BUR Licensing

Enclosure:

As stated cc: See next page bcc:

V. Benaroya R. Ferguson S. West i

r lio kg hh$j00 40 S. Brown F

PDR

0. Parr S. Black E. Weinkam 4)

W. Butler a

pBWR-PD#4/PM tD-t BWR-PD#4/D JStefano:1b WButler 11/4/85 11/19/85

..r UNITED STATES

.[

g

. NUCLEAR REGULATORY COMMISSION

g 2.

WASHINGTON, D. C. 20555

?%

NOV 2 91985 Docket Nos. 50-440/441

' Mr. Murray E.. Edelman Vice President - Nuclear Group

The Cleveland Electric Illuminating Company.

P.O. Box 5000 Cleveland, Ohio 44101-

SUBJECT:

' FIRE PROTECTION PROGRAM FSAR/ TECHNICAL SPECIFICATION CHANGES FOR THE PERRY NUCLEAR POWER PLANT In your. letter of November 15, 1985, you proposed to delete the fire protection

. program elements from the Perry Unit 1 Technical Specifications, and in lieu thereof, to document those elements in the FSAR. The staff finds this change, wherein you describe and control the fire protection program through the FSAR, to be acceptable, provided you retain the administrative controls related to the program as reflected in the enclosed markup pages of the November 12, 1985 final draft of the Technical Specifications. CEI is requested to certify the Perry, Unit 1 Technical Specifications implementing the changes reflected

.in the enclosure.

Should there b: any questions or need to discuss this matter further with the staff,.please b t me know.

i Sincerely, f,(ltl bl Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Enclosure:

As stated cc: See next page a

Mr. Murray R. Edelman Perry Nuclear Power Plant The Cleveland Electric-Units 1 and 2 Illuminating Company cc:

Jay Silberg, Esq.

Mr. Larry O. Beck Shaw, Pittman, & Trowbridge The Cleveland Electric 1800 M Street, N. W.

Illuminating Company Washington, D. C.

20006 P. O. Box 97 E-210 Perry, Ohio 44081

- Donald H. Hauser. Esq.

-The Cleveland Electric

-Illuminating Company-P. 0. Box 5000

-Cleveland, Ohio 44101 Resident Inspector's Office U. S. Nuclear Regulatory Commission Pannly at Center. Road Perry, Ohio _44081 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799' Roosevelt Road Glen Ellyn, Illinois 60137 Donald T. Ezzone, Esq.

Assistant Prosecuting Attorney 105 Main' Street Lake County Administration Center Painesville, Ohio 44077 Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry J. Lodge, Esq.

618 N. Michigan Street Suite 105 Toledo, Ohio 43624 John G. Cardinal, Esq.

Prosecuting Attorney Ashtabula County Courthouse Jefferson,;0hio 44047

FINAL HAFT

~

~~

~

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 3

PAGE SECTION INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation...............

3/4 3-70 Table 3.3.7.3-1 Meteorological Monitoring Instrumentation...................

3/4 3-71 Table 4.3.7.3-1 Meteorological Monitoring Instrumentation Surveillance Requirements......................

3/4 3-72 St$

C tRemote Shutdown System Instrumentation and Controls.....

3/4 3-73 r

L, g t LD 9

Table 3.3:7.4-1 Remote Shutdown System Instrumentation and Controls......

3/4 3-74 Table 4.3.7.4-1 Remote Shutdown System Instrumentation Surveillance Requirements......................

3/4 3-76 J

t Accident Monitoring Instrumentation.....................

3/4 3-77 r-,

il/

Table 3.3.7.5-1 Accident Monitoring Instrumen-tation............................

3/4 3-78 Table 4.3.7.5-1 Accident Monitoring Instrumenta-tion Surveillance Requirements....

3/4 3-80 3/4 3-81 Source Range Monitors...................................

3/4 3-82 Traversing In-Core Probe System.........................

enta {.

3-re D tio Inst bl 7

-1 F

De eti I trumen ion...

3-3/4 3-86 Loose-Part Detection System.............................

l Radioactive Liquid Effluent Monitoririg Instrumen-3/4 3-87 tation..................................................

Table 3.3.7.10-1 Radioactive Liquid Effluent Monitoring Instrumentation.......

3/4 3-88 Table 4.3.7.10-1 Radioactive Liquid Effluent Monitoring Instrumentation

~

l Surveillance Requirements........

3/4 3-90 l..

PERRY - UNIT 1 ix NOV 121985

~

P R W FT

~

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE '

PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY RECIRCULATION SYSTEM.............

3/4 7-3 i

3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...................

3/4 7-6 3/4.7.4 SNUBBERS................................................

3/4 7-8 Figure 4.7.4-l' Sample Plan 2) For Snubber Functional Test....................

3/4 7-13 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

3/4 7-14 7.6 FIRE SUPPRESSION SYSTEMS ire Suppression Water System..........................

3/4 7-16 Spra and/or Sprinkler Systems.........................

3/4 7-19 Tab 1 3.7.6.2-1 Spray d/or Sprinkler Systems....

3/4 7-20 e

CO Systems...........................................'

3/4 7-21 2

Table 3.7.6.3-1 ow Pressure CO Systems..........

3/4 7-22 2

3/4 7-23 Fire Hose Station.........

Table 3.7 4-1 Fire Hose tions................

3/4 7-24 Yard Fire drants and Hydrant Hose Hou 3/4 7-26 T le 3.7.6.5-1 Yard Fire Hydrants and Hy t

Hose Houses......,.......

...<..<- --3/4 7-27

,73/t.77 FIRE "ATED A3CEun[ Igg,,,,,,,,,,,,,,,,,,

3/A 7-M 3/4.7.6 MAIN TURBINE BYPASS SYSTEM..............................

3/4 7-30 3!4.7.9 FUEL HANDLING BUILDING 3/4 7-31 Fuel Handling Building Ventilation System...............

3/4 7-33 Fuel Handling Building Integrity........................

PERRY - UNIT 1 xiv NOV 121985 O

.-.-e a.ee e s==

4.**<=a.e.-,.

.mg a

FI R #"3FT BASES l

SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....................

8 3/4 3-4 Seismic Monitoring Instrumentation......................

8 3/4 3-4 Meteorological Monitoring Instrumentation...............

8 3/4 3-4 Remote Shutdown System Instrumentation and Controls.....

8 3/4 3-5

Accident Monitoring Instrumentation.....................

8 3/4 3-5 Source Range Monitors...................................

8 3/4 3-5 Traversing In-Core Probe System.........................

8 3/4 3-5 m,

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

8 3/4 3-6 J'-

Radioactive Liquid Effluent Monitoring

?:

x Instrumentation.........................................

8 3/4 3-6 s

Radioactive Gaseous Effluent Monitoring 8 3/4 3-7 Instrumentation.........................................

3/4.3.8 TURBINE CVERSPEED PROTECTION SYSTEM.....................

8 3/4 3-7 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION.................

8 3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water.

Leve1......................

8 3/4 3-8 3)4.4 REACTOR COOLANT SYSTEM 8 3/4 4-1 3/4.4.1 RECIRCULATION SYSTEM....................................

8 3/4 4-2 3/4.4.2 SAFETY / RELIEF VALVES....................................

3/4.4.3 REACTOR COOLANT SYSTEM LEAXAGE 8 3/4 4-3 Leakage Detection Systems...............................

8 3/4 4-3

~

Ope rati onal Leakage.....................................

8 3/4 4-4 3/4.4.4 CHEMISTRY...............................................

xix PERRY - UNIT 1 NOV 121985

. =..

Fina!. navy I

i 8ASES PAGE SECTION CONTAINMENT SYSTEMS (Continued) 3/4.6.2 DR WELL B 3/4 6-3 D rywel l I nteg ri ty.......................................

B 3/4 6-3 Crywell Bypass Leakage..................................

B 3/4 6-3 Drywell Air Lock........................................

B 3/4 6-4 Drywell Structural Integrity............................

B 3/4 6-4 Drywell Internal Pressure...............................

B 3/4 6-4 Drywell Average Air Temperature.........................

B 3/4 6-4 3/4.6.3 DEPRESSURIIATION SYSTEM 3................................

3/4.6.4 CONTAINMENT AND DRYWELL ISOLATION VALVES................

B 3/4 6-6 8 3/4 6-6 A

3/4.6.5 VACUUM RELIEF...........................................

Ul B 3/4 6-7 3/4.6.6 SECONDARY CONTAINMENT...................................

B 3/4 6-7 3/4.6.7 ATMOSPHERE CONTR0L......................................

s 3/4.7 PLANT SYSTEMS B 3/4 7-1 3/4.7.1 COO LING WATER SYSTEMS...................................

a B 3/4 7-1

'..1/(.7.'21 CONTROL ROOM EMERGENCY RECIRCULATION SYSTEM.............

REACTOR CORE ISCLATIDN. COOLING. SYSTEM....-

.......~, --. 8. 3/4 7-1. ---

3/4.7.3 E ?/4 7-2

3/4.7.-4 SNUBBERS................................................

B N4 7-3 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

3/4

.7.6 F

SUPPR 10 YST J

7-4

/4.

FIRE D ASSEMBL B 3/4 7-4 3/4.7.8 MAIN TUR8INE BYPASS SYSTEM..............................

B 3/4 7-4 3/4 7.9 FUEL HANDLING BUILDING..................................

p ni PERRY - UNIT 1 NOV 121985 s

.T.~.__-.

hh h

INSTRUMENTATION FIREMETECTIONINSTRUMENTATION LIMITI CONDITION FOR OPERATION 3.3.7.8 As minimum, the fire detection instrumentation far ach fire detection zon'e hown in Table 3.3.7.8-1 shall be OPERABLE.

APPLICABILITY:

enever equipment protected by the fire d ection instrument is required to be PERABLE.

ACTION:

a.

With the num er of OPERABLE fire detection struments in one or more zones:

1.

Less than, but more than one-half o, the Total Number of Instru-ments shown in Table 3.3.7.8-1 fo Function A, restore the in-operable Fun tion A instrument (s to OPERABLE status within.

14 days or, w hin I hour estab ish a fire watch patrol to in-spect the zone )/ area (s) wit the inoperable instrument (s) at least once per h ur, unless e instrument (s) is located inside the containment, en inspe that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> o monito the containment air temperature at least once per hour tt locations listed in Specification 4.6.1.7 and 4.6.2.6.

2.

One less than the Tota umber of Instruments shown in Table h-3.3.7.8-1 for Functic B, or one-half or less of the Total Number of Instruments show in T le 3.3.7.8-1 for Function A, or with any two or more ad cent i truments inoperable, within I hour establishafireyatchpatr1toinspectthezone(s)/ area (s) with the inoperable instrument (s) at least once per hour, unless the instrument (

is located 1Kside the containment, then inspect that containme t zone at least ce per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment r temperature at le st once per hour at the loca-tions liste in Specification 4.6.

7 and 4.6.2.6.

b.

The provisions f Specifications 3.0.3 an 3.0.4 are not applicable.

SURVEILLANCE REQUIREME S 4.3.7.8.1 Each of e above required fire detection inst ents which are l

accessible during nit operation with the exception of the ontrol room, Area J

ICC-Sa, shall be emonstrated OPERABLE at least once per 6 nths by performance of a CHANNEL FU TIONAL TEST.

Fire detectors which are not cessible during unit operation hall be demonstrated OPERABLE by the performa e of a CHANNEL FUNCTIONAL TE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> u ess performed

(

in the previ s 6 months.

4.3.7.8.2 he fire detection instruments in the control room, Are ICC-Sa, shall be monstrated OPERABLE at least once per 6 months by perfo nce of a CHANNEL F NCTIONAL TEST of at least 10% of the detectors and the test g shall be sche led such that all the detectors are tested at least once per 5 ears.

4.3.7

.3 The NFPA Standard 720 supervised circuits supervision associate with he detector alarms of each of the above required fire detection l

ins uments shall be demonstrated OPERABLE at least once per 6 months.

P RY - UNIT 1 3/4 3-83 NOV 121985

FINAL nMFT TABLE 3.3.7.8-1 FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION TOTAL NUMBER OF INS RUMENTS*

HEAT FLAME SMOKE Fire Zo / Area (x/y)

(x/y)

(x/y)-

A.

Reacto Building Unit 1 1.

IR8-15/0 0/

83/0 2.

1RB-1 39/0 0/

0/0 3.

1RB-Id 0/0 00 2/0 B.

Auxiliary Build Unit 1 1.

IAB-lb 0/0 0/0 9/0 2.

IAB-1c 0/0 0/0 2/0 3.

IAB-le 0/0 0/0 9/0 4.

IAB-Is 0/0 0/0 9/0 5.

IAB-2 0/0 0/0 20/0 6.

IAB-3a 0/0 0/0 9/0 7.

IAB-3b 0/

0/0 8/0 C.

Intermediate Building O

1.

IB-1 4/0 0/0 29/0 2.

18-2 0/0 0/0 31/0 3.

18-3 0/0 0/0 30/0 4.

18-4 0/0 0/0 42/0 5.

IS-5

/0 0/0 23/0 D.

Control Complex 0/0 0/0 41/0 1.

CC-la, Ib, Ic 2.

CC-2a 0/0 0/0 23/0 3.

CC-2b, 2c 0/0 0/0 28/0

'4'.

ICC-3a 0/0 0

7/0

'~

5.

ICC-3b 0/0 0

2/0 7/0

' " " '" " " " 0/0 * " ' '0/0 6.

ICC-3c 0/0 0/0 1/0 7.

ICC-3d

-8.

ICC-3e -

0/0 0/0 2/0 y,

9.

ICC-4a 0/18 0/0 7/0 10.

ICC-4b 0/18 0/0 6/0

11. ICC-4c 0/0 0/0 0

12.

ICC-4d 0/0 0/0 0

13. ICC-4e 0/18 0/0 7

14.

ICC-4f 0/21 0/0 7/0 15.

ICC-4g 0/0 0/0 1/0

16. ICC-4h 0/0 0/0 2/0 17.

ICC-41 0/0 0/0 8/0 336/0 0/0 202/0

18. ICC-5a 19.

ICC-5b 0/0 0/0 0/4

~

0/0 0/0 7/0 20.

ICC-Sc

(!

0/0 0/0 2/0 21.

CC-6 0/0 0/0 30/0 22.

ICC-6 NOV 121985 PERRY - UNIT 1 3/4 3-84

- - - - - + - - = -

h i

TABLE 3.3.7.8-1 (Continued)

O.

FIRE DETECTION INSTRUMENTATION I TRUMENT LOCATION TOTAL NUMBER INSTRUMENTS

• HEAT F

E SM0KE Fire e/ Area 57f) y 57il E.

Diese Generator Building j

1.

IDG a 2/6 0/0 3/0 1

2.

1DG-2/6 0/0 3/0 3.

IDG-Ic 2/6 0/0 3/0 4.

IDG-Id 0/0 0/0 3/0 F.

Emergency Service ater Pumphouse 1.

ESW-la 00 0/0 10/0 2.

ESW-lb

/0 0/0 1/0 G.

Fuel Handling Building 1.

FH-1 0/0 0/0 10/0

2.. FH-2a 0/0 0/0 7/0 l

3.

FH-2b 0/0 0/0 5/0 4.

FH-3 0/0 16/0 0/0

~

j

• (x/y): x is number of F nction A (early warning fire detection nd notification I

only) instrumen s.

l y is number of unction B (early warning fire detection an suppression only) instr ts.

1. The fire detection i struments located within the Containment are not equired to be OPERABLE duri the performance of Type A Containment Leakage Ra Tests.

~

PERRY - UNIT 1 3/4 3-85 NOV 121985

PLANT SYSTEMS

h. I 3/4 FIRE SUPPRESSION SYSTEMS FIRE SU ESSION WATER SYSTEM LIMITING C DITION FOR OPERATION 3.7.6.1 The fi suppression water system shall be OPERABL with:

a.

Two fire uppression pumps, each with a capacit of 2500 gpm, with their ischarge aligned to the fire suppr ssion header, b.

An OPERABLE ow path capable of taking sur. on from the ESW forsbay and transferri the water through distrib ion piping with OPERABLE sectionalizing ntrol or isolation valve to the yard hydrant curb valves, the last alve ahead of the wat flow alarm device on each sprinkler or hose tandpipe and the la valve ahead of the deluge valve on each delug or spray system quired to be OPERABLE per Specifications 3.7.6., 3.7.6.4, and

.7.6.5.

APPLICABILITY:

At all times.

ACTION:

a.

With one pump inoperable, re ore the inoperable pump to OPERABLE Jp status within 7 days or prov an alternate backup pump.

The provi-sions of Specifications 3..3 a d 3.0.4 are not applicable.

b.

With the fire suppressic water s tem otherwise inoperable, establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS I

\\

,4.7.6.1.1-The fire suppres on water system shall e demonstrated OPERABLE:

f At least once p r 31 days by starting the e ectric motor driven fire a.

suppressicn pu p and operating it for at lea t 15 minutes on

- recirculatio

flow, b.

At least o ce per 31 days by verifying that each anual valve in the flow ath is in its correct position.

(

PERRY - UNIT 1 3/4 7-16 NOV 121686

}N PLANTsSYSTEMS SURVEIL NCE REQUIREMENTS (Continued) 1m At 1 ast once per 12 months by cycling each testable valve in the th through at least one complete cycle of full travel, c.

flow At leas't nce per 18 months by performing a system functional t t

a which inc1 des simulated automatic actuation of the system thr ughout d.

its operati sequence, and:

east T

Verifying that each fire suppression pump develops at

}

1.

3750 gpm a a system discharge pressure of 81 psig.

2.

Cycling each alve in the flow path that is not stable during le of full l

plant operatio through at least one complete c travel, and fire suppression pump s arts (sequentially) 3.

Verifying that eac to maintain the fir suppression water sy em pressure greater

}

than or equal to 65 p ig.

}

At least once per 3 years by erformityg a ow test of the system in accordance with Chapter 5, Se ion 11 of he Fire Protection Handbook, e.

14th Edition, published by the 'ational ire Protection Association.

3 L".)

The diesel driven fire suppressi mp shall be demonstrated 4.7.6.1.2 OPERABLE:

At least once per 31 days by; a.

1.

Verifying the fuel day t k contai at least 150 gallons of fuel.

. _2.

Starting the pump fro ambient condit ns and operating for to 30 minutes on ecirculation flow.

greater than or equa At least once per 92 da s by verifying that a s mple of die'sel fuel from the fuel storage ank, obtained in accordan with ASTM-D270-75, b.

is within the accept le limits specified in Table of ASTM-0975-77 when checked for vi cosity, water and sediment.

18 months, during shutdown, by subje ting the diesel in conjunction c.

At least once pe to an inspectio in accordance with procedures prepare service.

with its manu cturer's recommendations for the class o 3/4 7-17 25 PERRY - UNIT 1

PLANT SYSTEMS SURVEILLA E REQUIREMENTS (Continued) x 4.7.6.1.3 Each esel driven fire pump starting 24-volt batt bank and charger shall be onstrated OPERABLE:

a.

At least.onc per 7 days by verifying that:

E 1.

The electr e level of each pilot c 1 is above the plates, I

2.

The pilot cell ecific gravity, c rrected to 77'F and full electrolyte leve is greater th or equal to 1.200, and 3.

The overall battery 1tage i greater than or equal to 24 volts.

.f f

b.

At least once per 92 days by r fying that the specific gravity is I

appropriate for continued serv of the battery.

c.

At least once per 18 months y veri ing that:

1.

The batteries and b tery racks sh no visual indication of physical damage or abnormal deterior fon, and 2.

Battery-to-bat ry and terminal connectio are clean, tight, free of corro on and coated with anti-corr fon material.

m

d;l l

S S

ee oe e

e a

.O e

M ed e#

G Nov 121sS5 3/4 7-18 PERRY - UNIT 1

=

.. ~;_

ea PLANT SYSTEMS SPRAY MND/OR SPRINKLER SYSTEMS 2

LIMITIN NDITION FOR OPERATION

/

\\

3.7.6.2 The wa r spray, preaction sprinkler and automati sprinkler systems listed in Table. 7.6.2-1 shall be OPERABLE:

APPLICABILITY: Who ver equipment protected by the w er spray, preaction sprinkler and/or auto atic sprinkler systems is requ ed to be OPERABLE.

ACTION:

a.

With one or more of the above require spray and/or sprinkler systems inoperable, withi one hour establis a continuous fire watch with backup fire suppres ton equipment f those areas in which redundant systems or component could be dam ged; for other areas, establish an hourly fire watch trol.

b.

The provisions of Specif atio 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE:.'}UIREMENTS 4.7.6.2 Each of the above required ate spray, preaction sprinkler and e%

cutomatic sprinkler systems shall demo strated OPERABLE:

O a.

At least once per 31 d s by veri ing that each valve, manual, or automatic, in the ow path is i its correct position.

b.

At least once per months by cyclin each valve in the flow path through at least o e complete cycle of ull travel.

c.

At least once p 18 months:

'1.

By perfo ing a system functional test ich includes simulated automat actuation of the system, and v ifying that the auto-l matic lves in the flow path actuate to t air correct posi-tions on a stem test signal.

2.

By visual inspection of the dry pipe spray d sprinkler ders to verify their integrity.

l 1

3.

y a visual inspection of each nozzle's spray are (except charcoal filter system spray nozzles) to verify th t the spray pattern is not obstructed.

d.

he charcoal filter system spray nozzles shall be visually inspected and verified to be unobstructed each time the charcoal is c nged.

l I

~

PERRY - UNIT 1 3/4 7-19 HOV121985 L-

_ = _ _.

.. =

Tcbla 3.7.6.2-1 II SPRAY AND/0R SPRINKLER SYSTEMS 3

TYPE OF i*

SYSTEM E

EQUIPMENT OR AREA PROTECTED Q

PANEL NO.

Water"$ pray

\\1M1500018 Unit 1AnnulusExhaustGasTreatmentPlenum lenum Water Spray 1H51-P126 14D001A Unit 1 Containment Vessel and Drywell Exhaus

,l IH51-P123 0018 Unit 1 Containment Vessel and Drywell Exh t Plenum Water Spray i

1H51-P124 1

Water Spray 1H51-P125 1M15D A Unit 1 Annulus Exhaust Gas Trgatment P1 um Water Spray H51-P120 M260001B ntrol Room Emergency Recirculation P num H51-P118 M260001A Co 1 Room Emergency Recirculatio Plenum Water Spray g

Control Comple

1. 599'-0" and Southeast orner E1. 574'-10" Sprinkler Water Spray i.

H51-P127 M400001A Fuel Han ing Area Exhaust P1 Water Spray

' H51-P128 M4000018 Fuel Hand 11 Area Exhaust enus Water. Spray H51-P129 M400001C Fuel Handling ea Exha Plenum Water Spray IH51-P116 1M380001 Unit 1 Auxiliary 11 ng Exhaust Plenum Sprinkler H

w Unit 1 Reactor Core Isolati ooling Preaction

)

Unit 1 Div. 1 Cable Spre ng R Preaction yl 1H51-P209 y

1 4

1H51-P210 Unit 1 Div. 2 Cable S ading Room Sprinkler Intermediate Build E1. 599'-0" Sprinkler l

o Intermediate Bu ing E1. 620'-6" Sprinkler ll Auxiliary Bu ing El. 620'-6" Preaction

t 2H51-P209 Unit 2 Div 1 Cable Spreading Room Preaction 2H51-P210 Unit 2

v. 2 Cable Spreading Room M

a.c=

I 253 e" 'i

'l 5

C"J 3

'Je yc2

=

M g

=m4 l

.g g r

PLANT SYSTEMS g

B Elk bw g SYSTEMS s

LIMITING CONDITION FOR OPERATION i

systems listed in Table 3.7.6.3-1 sh 11 be

3..

3 The low pressure CO2 OPE LE.

APPLICAB IH: Whenever equipment protected by the above req red CO systems 2

is requir~

to be OPERABLE.

7 ACTION:

With o e or more of the above required CO,s stems inoperable, within 1

a.

one hou establish a continuous fire watch ith backup fire suppres-8 ment for those areas in which r dundant systems or components sion equ r

could be maged; for other areas, esta ish an hourly fire watch patrol.

b.

The provisions of Specification 3.0.

and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.3.1 Each of the'above quired C0 systems shall be demonstrated

?h OPERABLE at least once per 31 ys by ifying that each valve, manual,

~

power operated or automatic, in he f w path is in,its correct position.

systems shall be 4.7.6.3.2 Each of the above requi d low pressure CO2 demonstrated OPERABLE:

storage tank capacity a.

At least once per 7 ys by erifying the CO2 and pressure to be reater th n:

. Tank Capacity (1

)

Pressure (psic)

OP54A008 5080 275 OP54A009 724 275 b.

At least on per 18 months by verify g:

I 1..

The ystem, including associated ven lation system fan trips, d

ers and fire door release mechanis

, actuates, f s simulated l

a nually and automatically, upon receipt e excluded from this release may ctuation signal, (actual CO2 test) and Test."

Flow from each accessible nozzle during a "Pu

[

(

3/4 7-21 ggg PERRY - UNIT 1

-e=.-=

. =

m Kablo3.7.6.3-1 Lcw Prcss re CO Systcas 2

System me Fire Zone / Area i

A.

Standby esel Gen ator IDG-la B.

HPCS Diesel G ator IDG-lb C,

Standby Diese Gene tor IDG-1c i

D.

Unit #1 Co rol Room ICC-Sa G

1 f

8 PERRY - UNIT 1 3/4 7-22 2S

-..m

PLA4T SYSTEMS FIRE SE STATI0'NS

[

LIMITIN ONDITION FOR OPERATION

/

\\

3.7.6.4 The tre hose stations shown in Table 3.7.6.4-1 sh be OPERABLE.

APPLICABILITY:

henever equipment in the areas protecte y the fire hose stations is requ ed to be OPERABLE.

i ACTION:

a.

With one or re of the fire hose statio shown in Table 3.7.6.4-1 inoperable, p vide gated wye (s) on the earest OPERABLE ho.se stations (s).

O outlet of the wye sh 1 be connected to the standard length of hose p vided for the hose ation.

The second outlet of the wye shall be c nected to a long of hose sufficient to provide coverage for the ar left unprotec ed by the inoperable hose station.

Where it can be demon trated that he physical routing of the fire hose would result in a ecogniza e hazard to operating technicians, plant equipment, or the ose it if, the fire hose shall be stored in a roll at the outlet o the PERABLE hose station.

Signs shall be mounted above the gated (s) to identify the proper hose to use.

The above ACTION shall be a emplished within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable m

of fire suppression; otherwise route fire hose is the pri'ary a n the additional hose withi 24 urs.

I V

b.

The provisions of Speci cations

.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.4 Each of the fire hos stations shown in ble 3.7.6.4-1 shall be demonstrated OPERABLE:

a.

At least once pe 31 days by a visual inspe ion of the fire hose

.' stations access ble during plant operation to assure all required equipment is the station.

b.

At least one per 18 months by:

- 1.

Visua inspection of the fire hose stations n accessible

~

~

~'

duri g plant operation to assure all required uipment is at the station.

2.

R oving the hose for inspection and re-racking, nd 3.

nspecting all gaskets and replacing any degraded skets in the couplings.

c.

At least once per 3 years by:

Partially opening each hose station valve to verify val OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure of 150 psi or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

PERRY - UNIT 1 3/4 7-23 c1

1 TABLE 3.7.6.4-1 FIRE HOSE STATIONS E

\\

OSE RACK LOCATION ELEVATION MPL NUMBER ESW Pu House 586'6" OP54-D566 OP54-D811 B

Unit #1 Rea or Building 599'9" 0P54-0730 OP54-0734 OP54-D5261 Unit #1 Reactor 11 ding 620'6" OP54-D731 OP54-D735 I

Unit #1 Reactor Bull ng 642'0" OP54-0736

~

OP54-D5262 Unit #1 Reactor Building 652' OP54-D737 Unit #1 Reactor Building 66 7"

OP54-D732 OP54-D738 Unit #1 Reactor Building 689'6" OP54-D733 OP54-D739 g,}

,O Fuel Handling Building 5

'10" OP54-D772 OP54-D773 Fuel Handling Building 599'0" OP54-D774 OP54-D777 Fuel Handling Building 620'6" OP54-D775

(

Auxiliary Building 568'4" IP54-D719 1P54-D5263 1P54-D5264 Auxiliary Buildi g 574'10" 1P54-D722 599'0" 54-D715 Auxiliary Buil ing 1 4-D718 l

1P -D721 I

Auxiliary uilding 620'6" 1P54-724 1P54-D 17 l

Inte

~diate Building 574'10" OP54-D75 OP54-D764

'/

OP54-D793

\\

3/4 7-24 PERRY - UNIT 1 NOV 121985 s

1 TABLE 3.7.6.4-1 (Continu 1

~

r HOSE RACK i

LOCATION

_ ELEVATION MPL NUMBER InthediateBuilding 599'0" 0P54-D7 6 OP54-765 OP54 792

. Intermedia Butiding 620'6" OP 4-D758 54-D766 P54-D794 Intermediate Buil ng 654'6" OP54-D759 OP54-D768 OP54-D795 Intermediate Building 682'6" OP54-D760 OP54-D769 OP54-D796 OP54-D770 Intermediate Building 707'6" Control Complex 574'10" OP54-D780 OP54-D783 0P54-D788 g

p b

Control Complex 5

'0" 0P54-D781 0P54-D784 OP54-D789 Control Complex 620'6" OP54-D1375 OP54-D5255 OP54-D5256 OP54-D5257 OP54-D1351

~

OP54-D1345 Control Complex 638'6" OP54-D1376 OP54-D1377 i

~

OP54-D5258 I

l OP54-05259 OP54-D1350 0P54-D1344 Control Comp 1 x 654'6" OP54-D1349 P54-D1343 Control mplex 679'6" 0 4-D1378 OP -D5260 OP D1348 OP54-1342 i

PERRY - UNIT 1 3/4 7-25

. ~. -. _

PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION FOR OPERATION l

3.7.6.5 The yard fire hydrants and associated hydrant hose houses hown in Table 3.7.

5-1 shall be OPERABLE.

APPLICABILI Whenever equipment in the areas protected by th yard fire hydrants is re ired to be OPERABLE.

ACTION:

a.

With one or ore of the yard fire hydrants or a ociated hydrant hose

~

houses shown n Table 3.7.6.5-1 inoperable, to a sufficient additional lengths of fi hose of equal or greater dia ter located in an adjacent OPERABLE hydran hose house to provide serv e to the unprotected

/. area (s) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

b.

The provisions of ecifications 3.0.3 d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

\\

/

4.7.6.5 Each of the yard fire hyd nts and sociated hydrant hose houses shown in Table 3.7.6.5-1 shall be de onstra d OPERABLE:

At least once per 31* days by i al inspection of the hydrant hose s.

' house to assure all required e ipment is at the hose house.

l b.

At least once per 6 months, urin March, April, or May and during l

September, October, or Nove ber, b visually inspecting each yard fire I

hydrant and verifying tha the hydra t barrel is dry and that the hydrant is not damaged.

c.

' ti least once per 12 m ths by:

1.

Conducting a ho hydrostatic test at a ressure of 300 psig or y __

at least 50 ps above the maximum fire a n operating pressure

~

~~

whichever is eater.

l l

2.

Replacement of all degraded gaskets in coupli s.

I 3.

Performi a flow check of each hydrant.

1..

K NOV121985 PERRY - UNIT 1 3/4 7-26 s.__. _ _

Mlg g! n M F T D

B#

TABLE 3.7.6.5-1 FIRE HYDRANTS AND ASSOCIATED HYD NT HOSE HOUSE 6 LOCATION HYDRANT MBER/ HYDRANT HOSE HOUSE NUMBERS Diesel Generator Building OP54-D 44 Diesel Generator Fuel Oil OP54 0543 Storage Tanks Unit #1 Startup Transformer 0P5 -0548 Unit #2 Startup Transformer OP 4-D539 7

b 3

b 3/4 7-27 PERRY - UNIT 1 N0y 121985

' ~ K '- :

• T ~~ ~ - -- -

~

PLANT SYSTEMS 3/4.7.7 FIRE RATED ASSEMBLIES E

S ' s Am LUCaC l

LIMITING CONDI ON FOR OPERATION

/

3.7.7 All fire bar ter assemblies, including walls, loor/ ceilings, cable tray enclosures and her fire barriers, separating safety related fire areas cr separating portion of redundant systems import nt to safe shutdown within a fire area, and all se ling devices in fire rat assembly penetrations, including fire doors, fi e dampers, cable, and ping seals, shall be OPERABLE.

APPLICABILITY:

At all tim ACTION:

i a.

With one or more of t above re utred fire rated assemblies and/or sealing devices inopera le, wit in one hour establish a continuous fire watch on at least o e si of the affected assembly (s) and/or sealing device (s) or veri e OPERABILITY of fire detectors on at least one side of the inop r ble assembly (s) or sealing device (s)

, and establish an hourly fir watch patrol.

b.

The provisions of Specifi ati ns 3.0.3 and 3.0.'4 are not applicable.

q;!

_.-W SURVEILLANCE REQUIREMENTS

/

\\

4.7.7.1 Each of the above re fred fire rate assemblies and penetration sealing devices shall be vari ied OPERABLE at 1 st once per 18 months by performing a visual inspecti n of:

- a.

rThe exposed surf es of each fire rated as embly, l

b.

Each fire damp and associated hardware.

cc.

At least 10 p rcent of each type of sealed pen tration.

If apparent changes in pearance or abnormal degradations re found, a visual inspection f an additional 10 percent of each t e of sealed penetratio shall be made.

This inspection proce s shall continue until a percent sample with no apparent changes in appearance or l

abnormal degradation is found.

Samples shall be se cted such that each p etration seal will be inspected at least one per 15 years.

l l

l PERRY - UNIT 1 3/4 7-28 NOV 121985

PLANT SYSTEMS SURVEILLANCE REQUIREME S (Continued)

Each of the above req f red fire doors sha be verified OPERABLE by 4.7.7.2 inspecting the automated hold-op n, release and c osing mechanisms and latches ct least once per.6 months, and b verifying:

The OPERABILITY of the fir door su rvision system for each a.

electrically supervised fir door performing a CHANNEL FUNCTIONAL TEST at least once er 1 days.

b.

That each locked-closed fire io is closed at least once per 7 days.

That doors with automatic h

-open a d release mechanisms are free l

c.

of obstructions at least c e per 24 h rs and by performing a functional test of these chanisms at 1 ast once per 18 months.

I d.

That each unlocked fire oor without electr al supervision is closed at least once p 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3/4 7-29 NOV 121985 PERRY - UNIT 1 l

1

~,

INSTRUMENTATION BASES j

MONITOMNG INSTRUMENTATION (Continued) 3/4.3.7.8 RE DETECTION INSTRUMENTATION OPERABILI f the detection instrume ation ensures that both adequate warning capabilit s available for prom detection of fires and that fire suppression systems, hat are actuated y fire detectors, will discharge extin-guishing agent in a ti ly manner.

P ompt detec, tion and suppression of fires will reduce the potentia for dama to safety-related equipment and is an integral element in the ov all cility fire protection program.

Fire detectors that are d to actuate fire suppression systems represent a more critically importan comp ent of a plant's fire protection program than detectors that are instal ed solel or early fire warning and notification.

Consequently, the minim number of RABLE fire detectors must be greater.

The loss of de etion capability for ire suppression systems, actuated

,by fire detectors epresents a significant egradation of fire protection for any area.

As a esult, the establishment of ire watch patrol must be initi-ated at an ear 1er stage than would be warranted r the loss.of detectors that provide on1 early fire warning.

The establishment frequent fire patrols in the aff cted areas is required to provide detection c ability until the A

inoperab e instrumentation is restored to OPERABILITY.

3/4.3.7.9 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.

The allowable out-of-service times and surveillance requirements are consistent with the recommen-dations of Regulatory Guide 1.133, " Loose Pa Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.'3). U RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor

.and control, as applicable, the releases of radioactive materials in liquid

~ ffluents during actual or potential releases of liquid effluents.

The alarm /

e trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instru-mentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous affluent instrumentation is provided to monitor and control, as applicabb, the releases of radioactive materials in gaseous Df effluents during actual or potential releases of gaseous effluents.

The alarm setpoints for these instrurents shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm will occur prior to exceeding PERRY - UNIT 1 B 3/4 3-6 NOV 121985

=.

~ -.

h g

BASES 3/4 7.6 FIhSUPPRESSIONSYSTEMS The OPERA LITY of the fire suppression systems e ures that adequate fire suppressiort apability is available to confine d extinguish fires cccurring in any p tion of the facility where saf y related equipment is located.

The fire s ression system consists the water system, spray cnd/or sprinkler syste

, CO systems, and fi hose stations.

The collective 2

capability of the fire su ression systems s adequate to minimize potential damage to safety related eq pment and i a major element in the facility fire protection program.

In the event that portions o e fire suppression systems are inoperable, alternate backup fire fighting e i ment is required to be made available in the affected areas until the i era e equipment is restored to service.

When the inoperabh fire figh ng equi ent is intended for use as a backup teans of fire suppression, longer perio of time is allowed to provide an alternate means of fire f hting than if th inoperable equipment is the primary means of fire s pression.

The surveillhne requirements provide assuran that the minimum OPERABILITY requir ents of the fire suppression syst s are met.

$ )

immediate co In the av t the fire suppression water system becom inoperable, ective measures must be taken since this syst provides the major fir suppression capability of the p1 nt.

3/4.7.7 FIR N D ASSEMBLIES x

The OPERABILITY o he fire b riers and barrier penetrations ensure that fire damage will be limite T se design features minimize the possibility of a single fire involving mo than one fire area prior to detection and e'xtingitishment.

The fire

criers, re barrier penetrations for conduits, cable trays and piping, re dampers, an e doors are periodically inspected

~

to verify their OPERA ITY.

N4.[.8M'AINTURBINEBPASSSYSTEM The main turbine bypass system is required to be OPERABLE consistent with the assumptions of the feedwater controller failure analysis in FSAR Chapter 15.

3/4.7.9 FUEL HANDLING BUILDING FUEL HANDLING BUILDING INTEGRITY ensures that the release of radioactive materials from the Fuel Handling Building follcwing a fuel handling accident will be. consistent with the accident analyses.

The Fuel Handling Building Ventilation Exhaust System ensures that no significant fraction of the radioactive release from a postulated fuel handling accident could escape

(

untreated.

PERRY - UNIT 1 8 3/4 7-4 NOV 121S65

b 6.0 ADMINISTRATIVE CONTROLS O

i 6.1 RESPONSIBILITY 6.1.1 The Manager, Perry Plant Operations Department, shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor or, during his absence from the control room, a designated individual shall be responsible for the control room command function.

A management directive to this effect, signed by the Vice President - Nuclear Group shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION CORPO. RATE 6.2.1 The corporate organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and:

Each on duty shift shall be composed of at least the minimum shift a.

crew composition shown in Table 6.2.2-1; b.

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

In addition, while the unit is ir. OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator shall be in the control room; A Health Physics Technician

• shall be on site when fuel is in the c.

reactor; d.

-ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during

_this operation; gade of at 1 st f e members shal e aintained on

e. ~ A s' e fire

~~

si e at all m

The re briga shall no nelude he Shift pervisor the Sh tT nical Advis nor e two othe embers of the mi imum shift w necessary for shutdown of the it and any ersonnel r utre r other e enti unctions during

(

fire ergency; a

• The Health Physics Technician d 'fr: brig d cri eciti n 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.

PERRY - UNIT 1 6-1

_ NOV 121985

L 39 f C7 ADMINISTRATIVE CONTROLS RESPONSIBILITIES

=

6.5.1.6 The PORC shall be responsible for:

a.

Review of all Administrative Procedures; b.

Review of the safety evaluations for (1) proposed procedure's/

instructions, (2) changes to procedures / instructions, equi ~pmint, systems or facilities, and (3) tests or experiments performed under the provisions of 10 CFR 50.59 to verify that such actions do not constitute an unreviewed safety question; Review of proposed procedures / instructions and changes to procedures /

c.

instructions, equipment, systems or facilities which involve an unreviewed safety question as defined in 10 CFR 50.59; d.

Review of proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; e.

Review of proposed changes to Technical Specifications or the Operating License; f.

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 Vice President -

Nuclear Group and to the Nuclear Safety Review Committee; g.

Review of all REPORTABLE EVENTS; h.

Review of the plant Security Plan and Security Contingency Instruc-tions and submittal of recommended changes to the Nuclear Safety Review Committee; i.

Review of the Emergency Plan and implementing instructions and sub-mittal of recomended changes to the Nuclear Safety Review Committee; j.

Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems;

" k '. ~~ Review of any accidental, unplanned or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations,' and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Managers, Perry

~'

' Plant Departments, the Nuclear Safety Review Committee and the i.

Vice President - Nuclear Group; 1.

Review of Unit operations to detect potential hazards to nuclear safety; andr Investigatiens or analysis of special subjects as requested by the m.

ChairmanoftheNuclearSafetyReviewCommittee4 d Y

A O

%MS e pw ' JA

%LR&

{.

(

Ce~ %-.

PERRY - UNIT 1 6-9 NOV12 585

Fin d. M P

~

ADMINISTRATIVE CONTROLS AUDITS (Continued) d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; The fire protection programmatic controls including the implementing e.

i procedures at least once per 24 months by qualified ifcensee QA personnel; f.

The fire protection equipment and program implementation at least

- M once per 12 months utilizing either a qualified corporate licensee fire protection engineer (s) or an outside independent fire protection consultant.

An outside independent fire protection consultant shall be utilized at least every third year;

~

p.

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

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; 1 ".

The PROCESS CONTROL PROGRAM and implementing procedures at least once per 24 months; 1

j.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months; and k.

Any other area of unit operation considered appropriate by the NSRC or the Vice President - Nuclear Group.

RECORDS 6.5.'59 Records of NSRC activities shall be prepared, approved, and distributed as indicated below:

4.

. Minutes of each NSRC meeting shall be prepared, approved, and l

-forwarded to the Vice President - Nuclear Group within 14 days following each meeting, b.

Reports of reviews er. compassed by Specification 6.5.2.7 shall be l

prepared, approved, and forwarded to the Vice President - Nuclear Group within 14 days following completion of the review.

c.

Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Vice President - Nuclear Group and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

MOV 12 M PERRY - UNIT 1 6-13

FDVMR ADMINISTRATIVE CONTROLS r:

6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 Written procedures / instructions shall be established, implemented, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide.1.33, Revision 2 February 1978.

b.

The applicable procedures required to implement the requirements of NUREG-0737 and supplements thereto.

c.

Security Plan implementation, d.

Emergency Plan implementation.

e.

PROCESS CONTROL PROGRAM implementation.

f.

OFFSITE DOSE CALCULATION MANUAL implementation.

\\

g.

Quality f.sssier.;: Pr gr= fer c"h: :t W environmental monitoring.

fueg f % n=citud fg MWM&

kcacn aaministrative p.q TAM vi 5pectrication 6.8.1, and changes

~6.8.2 us.uur.

thereto, shall be reviewed by the PORC and shall be approved by the Managers, Perry Plant Departments, prior to implementation.

All procedures / instructions shall be reviewed periodically es set forth in administrative procedures.

6.8.3 The following programs shall be established, implemented, nd maintained:

a.

Primary Coolant Sources outside Containment A program to re' duce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the HPCS, CS, RHR, RCIC, LPCS, feodwater leakage control system, and post-accident sampling systems.

The program shall include the following:

' 7-T 1.

Preventive maintenance and periodic visual' inspection requirements, and 2.

Integrated leak test requirements for each system at refueling cycle intervals or less.

l

-5 b.

In-Plant Radiation Monitorina l

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:

j 1.

Training of personnel, j

2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

i i

NOV12 ESS PERRY - UNIT 1 6-16

-