ML17277B321

From kanterella
Jump to navigation Jump to search
Proposed Tech Spec Changes Re Fire Detection Instrumentation
ML17277B321
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 03/09/1984
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17277B320 List:
References
NUDOCS 8403130330
Download: ML17277B321 (34)
v • d • e


Text

V 4 ~

INSTRUMENT LOCATION TABLE 3.3.7.9"1 FIRE DETFCTION INSTRUMENTATION TOTAL NUMBER" OF INSTRUMENTS ID SD TO UD SMO (x yy)

~(x y)

(x yy)

(x/y)

(x/y)

REACTOR BUILDING ELEV 422'"3" CRD PUHP ROOtl AUX COND.

PUtlP ROOM REACTOR BUILDING ELEV 441'-0" RAILROAD AIRLOCK REACTOR BUILDING ELEV 444'-0" RHR-2A PUMP RH R2 RHR"28 PUMP RM R1 RHR-2C PUMP RM R4 RCIC PUMP RM R3 LPCS PUMP RH R5 HPCS PUMP RM R6 REACTOR BUILDING ELEV 471'0" HCC ROOtl GENERAL AREA REACTOR BUILDING ELEV 501'-0" GENERAL AREA REACTOR BUILDING ELEV 522'"0 MCC ROOtl DIV. 2 GENERAl. AREA RHR VAl.VE ROOM REACTOR BUILDING ELEV 548'0 FUEL POOL HT.

EXCHGR ROOM A AND PUMP ROOtl GENERAL AREA RHR HT.

EXCHGR 8 ROOM REACTOR BUILDING ELEV 572'"0" HYDROGFN RECOMBIttER CONT.

RH OI%

2 RHR HT.

EXCHGR Rl'1 lA RHR HT.

EXCHGR RM 18 GENERAL FLOOR AREA REACTOR BUILDING ELEV 606'-10. 5" GENERAL FLOOR AREA RAOlrlASTE CONTROL BUILDING ELEV 467'-0" ELECTRICAL EQUIPMENT ROOM NO.

1 BATTERY ROOM NO.

1 SMITCHGEAR ROOM NO.

1 ELECTRICAL EQUIPMENT ROOtl NO.

2 BATTERY ROOM NO.

2 4/0 2/0 3/0 3/0 3/0 3/0 2/0 3/0 1/0 24/0 23/0 1/0 28/0 1/0 1/0 29/0 1/0 2/0 1/0 1/0 25/0 2/0 4/0 3/0 3/0 2/0 4/0

+i+~X'iQAtd MASHINGTON NUCLEAR " UNIT 2 3/4 3-80 8403130330 840309 PDR ADOCK 05000397 P

PDR

l I

~

p

INSTRUMENT LOCATION TABLE 3.3.7.9-1 (Continued)

FIRE DETECTION INSTRUMENTATION TOTAL NUMBER" OF INSTRUMENTS ID SO TO UD SMO

~(x P)

Yx/W).

VXX')

(x/Y)

(~Tv)

RADWASTE CONTROL BUILDING ELEV 467'-0" (Continued)

SWITCHGEAR ROOM NO.

2 3/0 REMOTE SHUTDOWN ROOM 1/0 CORRIDOR C"205 5/0 RAOWASTE ANO CONTROL BUILDING ELEV 484'"0 CABLE SPREADING ROOM 0/36 RAOWASTE ANO CONTROL BUILDING ELEV 501'"0" CABLE CHASE CONTROL ROOM (CEILING)

CONTROL ROOM (PGCC)

U679 U680 U681 U682 U683 U684 U685 U686 U687 0/5 12/0 8/0 11/0 7/0 6/0 8/0 6/0 6/0 8/0 8/0

" -~l/OI

., 0/9~

0/14~ o/I 0/8 0/8 0/8 0/8 0/8 0/8 U688 U689 U690 U800 U840 U891 U892 U893 U894~

RAOWASTE 6/0 4/0 5/0 5/0 5/0 8/0 8/0 9/0 8/0 AND CONTROL BUILDING E'V 525'-0" 0/8 0/8 0/8 0/6 0/6 0/8 0/10~ o/g 0/9 CABLE CHASE UNIT A - AIR CONDITIONING ROOM UNIT B " AIR CONDITIONING ROOM STANDBY SERVICE WATER PUMP HOUSE 1A PUMP HOUSE ELECTRICAL VAULT STANDBY SERVICE WATER PUMP HOUSE 18 PUMP HOUSE ELECTRICAL VAULT 0/6 5/0 5/0 1/0 1/0 1/0 1/0 2/1 2/1 WASHINGTON NUCLEAR - UNiT 2 3/4 3-81

PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The following pre-action and deluge spray and sprinkler systems shall be OPERABLE:

a.

Radwaste Building:

1.

Cable spreading room, elev. 484',

system ¹65.

2.

Cable chase and corridor, elev. 441'o 525',

system ¹66.

3.

Control Bldg. emergency charcoal filters, elev. 525',

system

¹WMA-OV-54A and WMA-OV-54B.

( +~~> ~~} eA'LV DD'LA Q)Q p&< c t.

OCTAL.s pmlg.

b.

Diesel Generator Building:

l.

2.

3.

5.

6.

OG room 1A and day tank room, elev. 441',

system ¹79.

OG lA day tank pump room, elev. 441',

system ¹80v DG room 1B and day tank room, elev. 441',

system ¹81.

DG 1B day tank pump room, elev. 441',

system ¹82.

HPCS DG room and day tank room, el ev. 441',

system ¹83.

HPCS OG day tank pump room, elev. 441',

system ¹84.

c.

Reactor Bui lding:

1.

Standby gas treatment system charcoal filters, elev. 572',

system ¹SGT-OIV-1A-1, ¹SGT-DIV-1A-2, ¹SGT-OIV-1A-3,

¹SGT-OIV-1B-l, ¹SGT-OIV-lB-2, and ¹SGT-OIV-1B-3.

2.

Sump vent filter system charcoal filters, elev. 572',

system

¹REA-DV-2A and ¹REA-OV-2B.

APPLICABILITY:

Whenever equipment protected by the spray and/or sprinkler systems 1s required to be OPERABLE.

ACTION:

a.

With one or more of the above required spray and/or sprinkler systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

WASHINGTON NUCLEAR - UNIT 2 3/4 7-21

TABLE 4.3.7. 11-1 (Continued)

TABLE NOTATIONS (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

l.

Instrument indicates measured levels above the alarm/trip setpoint.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when continuous, periodic, or batch releases are made.

(5)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

High voltage abnormally low.

3.

Instrument indicates a downscale failure.

WASHINGTON NUCLEAR - UNIT 2 3/4 3"88

~O r

I I

l I J

1 t

~

I

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued e.

For the AOS by:

l.

At least once per 31 days by verifying that the accumulator backup compressed gas system pressure in each bottle is

> 2200 psig.

2.

At least once per 31 days, performing a

CHANNEL FUNCTIONAL TEST of the accumulator backup compressed gas system low pressure alarm system.

3.

At least once per 18 months:

a)

Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating

sequence, but excluding actual valve actuation.

b)

Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 100 psig* and observing that, either:

1)

The control valve or bypass valve position responds accordingly, or 2)

There is a corresponding change in the measured steam flow.

c)

Performing a

CHANNEL CALIBRATION of the accumulator backup compressed gas system low pressure alarm system and verify-ing an initiation set oint of 140 ~psig on decreasing pressure an an alarm setpo>nt of 35 ~psig on decreasing

pressure, Verifying the nitrogen capacity in at least two accumulator bottles per division within the backup compressed gas system.

"The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

WASHINGTON NUCLEAR " UNIT 2 3/4 5-5

E H

D Ih li 4

I l~

t)

CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL DRYWELL AND SUPPRESSION CHAMBER HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6. 1 Two independent drywell and suppression chamber hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION: With one drywell and/or suppression chamber hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 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 />.

SURVEILLANCE RE UIREMENTS 4.6.6. 1 Each drywell and suppression chamber hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying during a recombiner system warmup test that the minimum recombine outlet temperature increases to greater than or equal to 500~F within 90 minutes.

b.

At least once per 18 months by:

1 ~

Performing a

CHANNEI. CALIBRATION of all recombiner operating instrumentation and control circuits.

C.

2.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test within 30 minutes following the above required functional test.

The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.

3.

Verifying during a recombiner system functional test that, upon introduction of 3X by volume hydrogen in a 140-180 scfm stream containing at least lX by volume oxygen, that the catalyst bed temperature rises in excess of 120'F within 20 minutes.

4.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e, loose wiring or structural connections, deposits of foreign materials, etc.

By measuring the system leakage rate:

1.

As a part of the overall integrated leakage rate test required by Specification 3.6, 1.2, or 2.

By measuring the leakage rate of the system outside of the containment isolation valves at P

, 34.7 psig, on the schedule required by Specification 4.6. 1.2, and including the measured a'eakage as a part of the leakage determined in accordance with Specification 4.6. 1.2.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-43

ll I

V e ~ s ~ >

4 I

~

I I,L y a

=

l ~ L Cl 1

"c

~

II ~ y Ik s

rwz Igw

ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL E UIPMENT PROTECTIVE DEVICES A.C.

CIRCUITS INSIDE PRIMARY CONTAINMENT LIMITING CONDITION FOR OPERATION 3.8.4.1 At least the following A.C. circuits inside primary containment shall be deenergized":

88R a.

Circuits supplied by breakers 2AR~and-28k, MCC E-MC-BC.

b.

Circuits supplied by panel E-LP-6BAG.

c.

Circuits supplied by panel E-LP-30AG.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With any of the above required circuits energized, trip the associated circuit breaker(s) in the specified panel(s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SURVEILI ANCE RE UIREMENTS

4. 8.4. 1 Each of the above required A. C. circuits shall be determined to be deenergized at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s*" by verifying that the associated circuit breakers are in the tripped condition.

6T-ec k @~5 gg LD ] Q(- 3X-)>

( erg I I+>

S~)P '<

I Except during entry into the drywell.

  • "Except at least once per 31 days if locked, sealed, or otherwise secured in the tripped condition.

WASHINGTON NUCLEAR " UNIT 2 3/4 8-20

TABLE 3. 8. 4. 2-1 PRIMARY CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE OEVICES

~EUIPMENT PRIMARY PROTECTION BACKUP PROTECTION a.

6900V Circuit Breakers RRC-P-1A E-CB-RRA (Relay)

RRC"P"18 E-CB-RRB (Relay b.

480VAC Fused Oisconnects E-CB"S5 E"CB"S6 (Relay)

E-CB-N2/5 (Relay)

(Relay)

E-CB-N2/6 (Relay)

RRC-V"67A RCC"V"71A KCC y-72&j-,RCC-V-72A P~C.gC7 CRA-FN"lc-2 RRC-V-678 RRC-V-238 RWCU-V-102 RWCU-V-106 RRC"V-23A RWCU"V"101 RWCU"V"100 RCC"V"178 RCC-V-71C RCC"V-718 CRA-FN-1A"2 MC-7C HC"7C MC"7C MC"7C MC"88 MC-SC MC"SC HC"SC MC"8C HC-SC MC-8C MC"BC MC"SC MC-8C MC"SC MC-78 25AF MC-7C 50AF-PIC OAF MC-7C 25AF 3.I~4 ~AF]'~gAP HC-7C ~ggcg5AF ~5P~

I,9-~ ~AF --i MC"7C 25AF

--~

110AF

~ <~~~

%68~se4- > ~

25AF HC-&4&41 14QSA Asst X+~I

/5 &AF ec-Ict'~l 440@~% ~&~~

5AF

~C-W~

X088A-Abet ~S AF 3AF M<4<~1 X8~set R<AF lAF 3AF 4bek 17eeeA-Ae.st

>5AF 3AF

~c-~'St-el

+eeeM~t ~5+~

1. 25AF n<<c~l l~~~t 2.5A~
1. 25AF n c-5~

aeee~e iSA~

I00 ~AF MC-78 ~ woe RI-CRA"fN-1A"1 CRA"FN-2A-2 CRA"FN-2A-1 CRA"FN-5A CRA-FN"4A CRA-FN-5C

- -CRA-FN-3A CRA"FN"18-2 CRA"FN-18" 1 CRA"FN"lc-1 CRA-FN-28-1 CRA-FN"28-2 MS-V-16 RWCU"V-1 RHR-V-9 RCIC-V-63 RCC-V"40 RHR"V-1238 MC-78 MC"78 MC-78 MC"78 MC"78 MC-,78 MC-78 ebb EieAF 4056AF Igo ~AF 25AF 15AF 25AF

.25AF MC-88 lb'AF MC-88 I<<%AF MC-88 IOQ 74@A%

MC-88

) $0 i&NF MC-88 60 OAF MCQ-,SB-A ~.S ~AF MC-88-A 5.6AF HC-88-A 15AF MC-88-A 15AF HC-88-A 3'AF MC"88"A

1. 125AF MC-78 HC"78 MC"78 at-'18k&

et -78SL" 71 r c-1~1 ee-16'.-+1 MC-88 HC"SB MC-SB fnGQif' p5$~1 MC-88 MC"88 HC-88 MC-88 HC-88 MC-88 SeAF a~~I'0AF Sb~hF SeeA-Aest ~o AF QOOA-Asst ~-c AF 888~t Sc AF SQQA-Ae~ 5a AF 1400A-Ac@4 9~8 ~

1,asm~~ BOA>

125AC8 125AC8 125AC8 125ACB 125ACB 125AC8 WASHINGTON NUCLEAR - UNIT 2 3/4 8-23

TABLE 3.8.4. 2-1 (Continued)

PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E UIPHENT PRIMARY PROTECTION BACKUP PROTECTION RCIC-V"76 CRA"FN-5B CRA-FN-50 CRA-FN-3B CRA-FN"3C CRA-FN"4B RCC-V"72B MS-V-1 MS"V"2 MS"V"5 RHR"V-123A MC-88"A MC-BB HC-8B HC-8B MC-8B MC-8B MC-8C HC-BC-B MC-8C-8 MC-BC-B MC-8B-A 25AF 25AF 25AF 25AF 15AF

l. 25AF IAAF

~4AF f4AF I.n82-.RSAF MC-8B Inc-gP~

AcgB~3.

mcgfQ~

rAMS&L-&3.

mc.g]~~

SL-81 MC-8C-8 MC-8C-8 HC-BC-P

~cgB Mmg.

125ACB

~ceo-a.~t>>~+

1868~++4 ~P'+

%00~k +bAF k969A-A.W 2.5 AF 1000A Asst see~ >SR~

ace~

>shF 2eeee ~~~

125ACB MASHINGTON NUCLEAR " UNIT 2 3/4 8-24

a ~

I H I4 ~

ply I ~

0

TABLE 3. 8. 4. 3-1 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION

'a ~

b.

C.

VALVE NUMBER CAC-V-2 CAC"V-4 CAC"V-6 CAC-V"8 CAC-V-11 CAC-V"13 CAC-V-15 CAC"V-17 CIA-V-20 CIA"V-30A CIA"V-30B F PC-V-153 FPC-V-154 FPC-Y-156 HPCS-V-1 HPCS-V-4 HPCS-V-10 HPCS-V-ll HPCS-V-12 HPCS-V-15 HPCS-V-23 LPCS-V-1 LPCS-V-5 LPCS-FCV-11 LPCS"V-12 MS"V"1 MS-V"2 MS-V-5 MS-V-16 MS-V-19 MS-V-20 MS-V-67A MS"Y-67B MS-V-67C MS"V-67D MS-V-146 SYSTEM(S)

AFFECTED Containment Atmospheric Control System Containment Instrument Air System Fuel Pool Cooling System High Pressure Core Spray System Low Pressure Core Spray System Main Steam System h.

RCC-V-5 RCC-V-6 RCC-V-17A RCC-V-17B RCC-V-21 RCC-V-40 RCC-V-71A RCC-V-71B RCC-V-71C RCC-V-72A RCC-V-72B RCC-V-104 RCC-V-129 RCC-V-130 RCC-V-131 i.

RCIC-V-1 RCIC-V-8 RC IC-V-10

-RCQ~~

RCIC-V-13 RC IC-V-19 RC IC-V-22 RC IC-V-31 SYSTEM(S)

VALVE NUMBER MSLC-V-lA MSLC-V-1B MSLC-V-1C MS LC-V-1D MSLC-V-2A MSLC-Y-2B MSLC-Y-2C MSLC-V-2D MSLC-V-3A t1SLC-V-3B MSLC-V"3C MSLC-V-3D MSLC-V-4 MSLC-V-5 MSLC-Y-9 MSLC-V-10 AFFECTED Main Steam Isolation Valve Leakage Control System Reactor Closed Cooling Water System Reactor Cor e Isolation Cooling System WASHINGTON NUCLEAR " UNIT 2 3/4 8-26

~ r

>>II Il>>l IIIIII

>>II~ III~

~IIII~IV

~ I

  • ~

~

~

~

>>II~ I I ~ ~

I

~

'I

~I t

~~ >>cI>

TABLE 3.8.4.3-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NUMBER SYSTEM(S)

AFFECTED SYSTEM(S)

VALVE NUMBER 'FFECTED RCIC-Y-45 RCIC-V-46 RCIC-Y-59 RCIC"V-63 RCIC-V-68 RCIC-V-69 RCIC-V-76 RCIC-V-110 RCIC-V-113 RFW-V-65A RFW-V-65B RHR-V-3A RHR-V-3B RHR-V-4A RHR-V-4B RHR-V-4C RHR-V-6A RHR-V-6B RHR-V-8 RHR-V-9 RHR-Y"16A RHR-V-16B RHR-V-17A RHR-V-17B RHR-Y-21 RHR-V-23 RHR-V-24A RHR"V-24B W~~B.

RHR-V-27A RHR-V-27B "RHR-V-40 RHR-V-42A RHR-V-42B Reactor Core Isolation Cooling System Reactor Feedwater System Residual Heat Removal System m.

RHR"Y-42C RHR-V-47A RHR-V-47B RHR-V-48A RHR-V-48B RHR-V-49 Mf~~h RHR-V"53A RHR-V-53B RHR-V-64A RHR-V-64B RHR-V"64C RHR-V-68A RHR-V-688 RHR-V-73A RHR-V-74A RHR-V-74B

~A RHR-V-115 RHR-V"116 RHR-V-123A RHR-V-123B RHR-V-134A RHR-V-134B RRC-V-16A RRC"V-16B RRC-V-23A RRC-V-23B RWCU-V-1 RWCU-V-4 RWCU-V-31 RWCU-V-34 Reactor Recirculation System Reactor Water Cleanup System WASHINGTON NUCLEAR - UNIT 2 3/4 8-27

~ t

~ t

~ t t ~

t

~

Wt At t'4 ~

\\ ~

t

~

~ ~

~ A

\\ ~

A t ~ t

~

~ ~

1

% ~

~

~

~ t tlA ~

> r

~ t

~ t

~

t A

  • 4 t

~ ~

~ ~

A 0zz A

I I

z sszsLII gfMcsHC

~VIEfHiENEfHHf5NS'IRECTOR dp 7'orr~

g~gi> v~i..~ S

~NOb66Y-OIRECTOR MANAGING DIRECTOR OEPUTY MANAGINGDIRECTOR TECHNICAL DIRECTOR CHIEF FINANCIAL OFFICER SUP SER DIR LICENSING AND ASSURANCE OIRECTOR

~ppor l geey i'cef LairiC 4C TECHNICAL TRAINING MANAGER OPERATIONAL ASSURANCE PROGRAMS MANAGER AUDITS MANAGER OFFSITE ONSITE PLANT MANAGER PLANT OA MANAGER tIUCLEARSAFETY ASSURANCE MANAGER FIGURE 6.2.1-1 OFFSITE ORGANIZATION

)(,

I~ $

4 r sr I

P" ~

C

NUCLEAR SAFETY ASSURAtlCE MANAGER WNP-2 PLANT MAtlAGER ASSISTANT PLANT MANAGER PLANT SECURITY SUPERVISOR TECHNtCAL TRAINING MIMIAGSR

~okOu/~Q SECURITY FORCES I LAIITOUAuTY ASSURAIICE MANAGER'NDUSTRIAL SAFETY SUPERVISOR TECHNICAL MANAGER IIP/CHEMISTRY MANAGER ADMINISTRATIVE MANAGER OPERATIONS MAtlAGER MAINTENANCE MANAGER REACTOR EtIGINEERIHG SUP/RVISOg Q~'T t y w~tL6

+vPUg. X IICAtttt PHYSICIST.

IIP SUPERVISOR (SRO) gC,nqru pe~i/

Ctt~

%<<<<P<<AT I'vpVP, Pt o ooIr~~~ Cd}

Nae~ge,r MECHANICAL SUPERVISOR ELECTRICAL SUPERVISOR PI gf.m~1 E <<Vd<<L6

+VIIUILW CHEMISTRY SUPERVISOR LEGEND INSTRUMENT SUPERVISOR PLANNINGI SCHEDULER NRC UCENSE RKOUtRED POSITION ISRO)

Sl'ARE P ERVISOR ADMINISTRATIVEAND FUNC'TIONALREPORTING LINE OF COMllUtIICATION MANT.SERVICES SUPERVISOR FIGURE 5.2.2.1 ~

UNIT ORGANIZATION

~ p.

f If 4

1llI II I<<'8 ~

ADMINISTRATIVE CONTROLS

6. 4 TRAINING 6.4.1 A retraining and replacement trai ng program for the unit staff shall be maintained under the direction of the Training 46P4fer-,"&all meet or exceed the requirements and recommendations of Section 5.5 of ANSI/ANS N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS COMMITTEE (POC)

FUNCTION 6.5. 1. 1 The POC shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POC shall be composed of the:

Chairman:

Vice Chairman:

Member:

Member:

Member:

Member:

Member:

Member:

ALTERNATES Plant Manager Assistant Plant Manager Operations Manager Technical Manage~

Maintenance Manager Administrati e Manager Plant gA Manager Health Physics/Chemistry Manager 6.5. lv3 All alternate members shall be appointed in writing by the POC Chairman or Vice Chairman to serve on a temporary basis.

MEETING FRE UENCY 6.5. 1.4 The Plant Operations Committee shall meet at least once per calendar month and as convened by the POC Chairman or his designated alternate.

gUDRUM 6.5.1.5 The quorum of the POC necessary for the performance of the POC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates.

No more than two alternates shall make up the quorum.

WASHINGTON NUCLEAR - UNIT 2 6"8

C

~

ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The POC shall be responsible for:

a.

b.

C.

d.

e.

g

.,P;...l., l'p./;~s h.

Review of (1) all proposed procedures required by Specification 6.8 and changes

thereto, (2) all proposed programs required by Specifica-tion 6.8 and changes
thereto, and (3) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; Review of all proposed tests and experiments that affect nuclear safety; Review of all proposed changes to the Appendix A Technical Specifications; Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evalua-.I k and to the Corporate Nuclear Safety Review Board;

, Z.

~

.C'.ll, p /LI -. 7.~.(.:. l~.

p<<l.( I IV J

Review of unit operations to detect potential hazards to nuclear saf ety; Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Corporate Nuclear Safety Review Board; Review of the Security Plan and implementing procedures and submitta'i of recommended changes to the Corporate Nuclear Safety Revie~ Board; k.

Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Corporate Nuclear Safety Review Board>

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 ;I.A and to the Corporate Nuclear Safety Review Board> <~4 Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.

AUTHORITY 6.5,1.7 The POC shall:

a.

Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5. 1.6a.

through d. prior to their implementation.

MASHINGTQN NUCLEAR - UNIT 2 6"9

1 CII t

~'

I

~

h 4

~

AW I

,r

AOMINISTRATIVE CONTROLS AUTHORITY (Continued) b.

Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6a.

through e. constitutes an unreviewed safety question~ c.s eel'~ed

> ioeva.sc.ss.

g6&.O +bee Ph,anbjir q 0 ~c'ccrc<~

7 QeneraHen and the Corporate Nuclear Safety Review Board of disagree-ment between the POC and the Plant Manager;

however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.3..1.

RECOROS A&biaV5a t Direc 4~

Qqg.c WiO~

6.5. 1.8 The POC shall maintain written minutes of each POC meeting that, at a minimum, document the results of all POC activities performed under the responsi-bility provisions of these Technical Specifications.

Copies shall be provided fto the ratio~nd the Corporate Nuclear Safety Review Boar d.

6.5.2 CORPORATE NUCLEAR SAFETY REVIEW BOARD CNSRB FUNCTION 6.5.2. 1 The CNSRB shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy, e.

Instrumentation and control, f.

Radiological safety, g.

Mechanical and electrical engineering, and h.

equality assurance practices.

The CNSRB shall report to and advise the Managing Director on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

~

WASHINGTON NUCLEAR - UNIT 2 6"10

I'

'I

~ a

<o.~ =~(~

4 l,]/p

~

w g

. i ~ e, r t

~

8t 4~

/

AOMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The CNSRB shall be composed of nine members appointed in writing by the Managing Oirector from his senior technical staff and/or from outside the Supply System.

He shall designate from the members, a Chairmarf;/Alternate h

Y

  • I The qualifications of all members shall meet the minimum requirements of Section 4.7 of ANSI/ANS 3. 1-1981 and have, cumulatively, expertise in the areas listed in Speci ication 6.5.2.1, as a minimum.

phd<+ oc.pan'~a+io~ aIM %he.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNSRB Chairman to serve on a temporary basis;

however, no more than two alternates shall participate as voting members in CNSRB activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNSRB Committee to provide expert advice to the CNSRB.

MEETING FRE UENCY 6.5.2.5 The CNSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.

UORUM 6.5.2.6 The quorum of the CNSRB necessary for the performance of the CNSRB review and audit functions of these Technical Specifications shall consist of the Chairman or the alternate Chairman and at least four CNSRB members includ-ing alternates.

No more than a minority of the quorum shall have line respon-sibility for operation of the unit.

REVIEW 6.5.2.7 The CNSRB shall review:

a 0 b.

The safety evaluations for (1) changes to procedures, equipment or systems and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; WASHINGTON NUCLEAR - UNIT 2 6-11

ADMINISTRATIVECONTROLS AUDITS (Continued) h.

The fire protection equipment and program implementation, at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant.

An outside independent fire protection consultant shal'l be utilized at least once every third year; and i.

Any other area of unit operation considered appropriate by the CNSRB or the Managing Director.

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

k.

RECORDS The QFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

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

6.5.2.9 buted as Records of CNSRB activities shall be prepared,

approved, and distri-indicated below; a.

C.

Minutes of each CNSRB meeting shall be prepared,

approved, and forwarded to the Managing Director 14 days fol'lowing each meeting.

Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared,

approved, and forwarded to the Managing Director within 14 days following completion of the review.

Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Managing Director and to the management positions responsible for the areas audited within 30 days after completion of the audit, 6.6 REPORTABLE EVENT ACTION 6.6. 1 The following actions shall be taken for REPORTABLE Events:

gis c4+f 4 l(S P/

Giimqq-OSS a ~

b.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.?3 to O CF P

, and URRENCE requiring 24-hour notificatio Commission shall be revlewe results of thss review shall b

e CNSRB and the Direc or on.

Each REPORTABLE EVENT shall. be reviewed by the

POC, and the results 1 hf, I

h111 hfh dh h

hhhh d

h WASHINGTON NUCLEAR - UNIT 2 6-13 gee; dine RI JY/edf+.,'~lfeelM dehe

~pefhhl fee <

ADMINISTRATIVE CONTROLS

6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

C.

d.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The

@i~i>~ /@~J;.z 4eR~&en and the CNSRB shall be notified, A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the POC.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components,

systems, or structures, and (3) corrective action taken to prevent recurrence.

The Safety Limit Violation Report shall be submitted to the Commission, the

CNSRB, and the v@WAsA

<~;.l~~P An~,.~5 W'r.~*~ 4. op<<.F'~~~-

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8. 1 Written procedures 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.

C.

d.

g.

h.

k.

Refueling operations.

Surveillance and test activities of safety-related equipment.

Security Plan implementation.

Emergency Plan implementation.

Fire Protection Program implementation.

PROCESS CONTROL PROGRAM implementation.

OFFSITE DOSE CALCULATION MANUAL implementation.

guality Assurance Program for effluent and environmental monitoring.

Health Physics/Chemistry Support Program.

6.8.2 Each procedure of Specification 6.8.1a.

through j., and changes

thereto, shall be reviewed by the POC and shall be approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

~gj...g/.,e.,r

- J pp--I.s

<<e

~ implementing procedures supporting item k. in Specification 6.8. 1 will be who will provide review and approval control.

The WNP-2 Health Physics/Chemistry Support Program procedure will be reviewed by POC and approved by the Plant Manager.

WASHINGTON NUCLEAR - UNIT 2 6"14

~e

,l g, I

AOMINISTRATIVE CONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9. 1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT 6.9.1. 1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating

License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel
supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

6.9. 1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions.

Any corrective actions that were required to obtain satisfactory opera" tion shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9. 1.3 Startup reports shall be submitted within (1) 90 days following completion of the star tup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the startup report does not cover all three events (i.e., initial criticality, compl'etion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS@

6.9. 1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality, "A single submittal may be made for a multiple unit station.

The submittal should combine those sections that are common to all units at the station.

WASHINGTON NUCLEAR - UNIT 2 6-16

~

g i

1 4

~.i P tW

~ s

Retrieved from "https://kanterella.com/w/index.php?title=ML17277B321&oldid=5099744"