Text

Amend 9 to License NPF-3,changing Tech Specs 3.3,3.7,4.3,4.7 & 6.1-.10 to Incorporate Limiting Conditions for Operation & Surveillance Requirements for Fire Protection Sys & Administrative Controls
	ML19317F684
Person / Time
Site:	Davis Besse
Issue date:	03/22/1978
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML19317F680	List: ML19317F679; ML19317F684; ML19317F686; ML19317F689;
References
	NPF-03-A-009 NUDOCS 8001230583
	Download: ML19317F684 (36)
	v • d • e

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UNITED S TATES of' f.,* j,,,

NUCLEAR REGULATORY COMMISSION

(*4.M WASHINGTON, O. C. 20555 9, %&

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'lilE 'IOLEDO EDISOd COMPANY A*JD THE CLEVELAtID ELECTRIC ILLUMINATING COMPANY DOCK 2r 10. 50-346 DAVIS-BESSE NUCLEAR POWER STATIOil, UNIT NO.1 AMENIXtENT 'IO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-3 1.

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

A.

The f acility will operate in conformity with the acplication, the provisions of the Act, and the rules and regulations of the Commission; B.

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragrarh 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as specified 5elcw.

2.C.(2) Technical Soecifications The Technical Soecifications contained in Appendices A and B, as revised through Amendment No. 9, are hereby incorporated in the license.

Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

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' The provisions of Specification 4.0.4 are not a,plicaole to the performance of surveillance t

activities associated with fire protection technical specifications 4.3.3.8, 4.7.9.1, 4.7.9.2, 4.7.9.3 and 4.7.10 until the completion of the initial surveillance interval associated with eacn specification.

3.

Tnis license a,tendraent becomes ef'fective 30 days af ter the date of i

issuance.

NR TiB NUCLEAR REGULAIORY COMISSION r>

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l Jonn F. Stelz, Chief Light Nater' Reactors eranen No. 1 Division of Project Management Attacntnent:

Changes to the Techrical

]

Specification?

MAR a " W' G Date-of Issuance:

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ATTACIE4DC 'IO LICENSE A'4EEMER NO. 9 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Revise Appendix A Technical Specifications as follows:

Change Pages Add Pages B 3/4 3-3 3/4 3-52 B 3/4 7-6 3/4 3-53 6-1 3/4 3-54 6-3 3/4 3-55 6-5 3/4 3-56 6-11 3/4 7-38 thru 7-47 6-13 6-19 6-20 The revised and new pages are identified by Amendx.ent number and contain vertical lines indicating the area of change. The corre-sponding overleaf pages are also provided to maintain document completeness.

m INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION t

3.3.3.7 The chlorine detection system, with the alarm / trip setpoint adjusted to actuate at a chlorine concentration of < 5 ppm, shall be OPERABLE with at least two OPERABLE chlorine detectors located in the Reactor Control Room ventilation air intake.

APPLICABILITY:

1, 2, 3 and 4 ACTION:

I a.

With one chlorine detector or the chlorine' detecticn system inoperable, within 1 hcur initiate and maintain operation of the control room ventilation system in the recirculation mode of operation; restore the inoperable detection system or detector to OPERABLE status within 30 days or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

The provisions of Specification 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.3.3.7 The chlorine detection system shall be demonstrated OPERABLE by performance of 3 CHANNEL CHECK at least cnce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST st least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

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_3 DAVIS-BESSE UNIT 1 3/4 3-51 A

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_If1STRUMEllTATI0fl uo D

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F_ IRE DETECT!0il IllSTRUMEilTATI0f1 l

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v LIMITIllG C0tiDIT10il FOR OPERATIO:4 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-14 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTI0ft:

With one or more of the fire detection instrument (s) shown in Table 3.3-14 inoperable:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the accessible zone (s) with the inoperable instrument (s) at least once per hour, and b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Spec-fication 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 i

days outlining _the action taken, the cause of the inoperability j

and the plans and schedule for restoring the instrument (s)-to OPERABLE status.

The provisions of Specifications 3.0.3 and 3.0.4 are not c.

applicable.

SURVEILLAl4CE REQUIRE!E?iTS t

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4. 3. 3. 8.1 Each of the above required accessible fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHAil WL FU!'CTI0i!AL TEST. Each of the above required inaccessible fire detection instrucent shall be demonstreted OPERABLE at least once per 18 months by performance of a CHAfitlEL FUilCTIOilAL TEST.

I 4.3.3.8.2 The ilFPA Code 720 Class A supervised circuits supervision ssociated with the detector alarms of each of the above required fire adetection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.8.3 The non-supervisca circuits t'etween the local panels in Specification 4.3.3.8.3 and the control rcom shall be demonstrated OPERACLE at least once per 31 days.

DAVIS-BESSr. U;lT 1 3/4 3-52 Amendment flo. 9

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Table 3.3-14 (Sheet 1)

FIRE DETECTION IflSTP.UMEtlTS flumber Number Required Type of Detecto. Tag-Instrument Location Installed T_o be Operable Detectors Number 1.

Containment cm

'U

.3.

Air Cir.-l*

1 1

I DS-0637C N

b.

' Air Clr.-2*

1 1

1 DS-3637A

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c.

Air Clr.-3*

1 1

I CS-3637B 5

d.

Re CIRC. Pan E.*

1 1

I D5-06363

)

G e.

Re circ. Pan W.*

1 1

I DS-&U6A f.

Pr zr/Htr*

1 1

I DS-8635 9

RC Pmp.-l*

1 1

I DS-8624A h.

RC Pmp.-2*

1 1

I D5-06248 i.

.RC Pmp.-3*

1 1

I DS-8625A j.

RC Pmp.-4*

1 1

I DS-8625B k.

Anis. Spac*

4 4

I DS-8644A-D 2.

Control Room (rm 502) 16 3 In Main Control I

DS-8616C & DS-3631A-C.

1 Board Cabinets m2 5 In Control

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Cabinet Room u

3.

Cable Spread Rm. (rm 422A) 6 6

I DS-8627A-G 4.

Computer Rm. (rm 510) 1 1

I DS-8632 5.

HV Swgr.'Rm. E. (rm 325) 2 2

I DS-8611A & B k

6.

HV Swgr. Rm. W. (rm 323)

.3 3

I DS-8612A, B, & C 7.

LV Swgr. Rm. E. (rm 429) f'2

'2 I

DS-8615A & B i

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8.

LV Swgr. Rm. W. (na 428) 2 2

I DS-8616A & B-o 9.

Aux. Shutdown Pnl. (rm 324) 1 1

I DS-8617 o

10. Station Bat. Rm. (rm 4298)

I l-I(DUCT)

DS-8613

Fire Detectors In lligh Radiation Areas Which Arc flot Accessib1c.

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JIRE DETECTIO;l I!!STRU?*ErtTS p

'is flumber flumber Required Type of Detector Tag Instrument Location Installed

.To be Operable Detectors Number di U

11. Station 8at. Rm. (rm 428A) 1 1

I(duct)

DS-8614 l

.12.

E!:DG'l (rm 318) 5 5

PE-DS-8605A-E

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13. D!DG-2 (rm 319) 5 5

PE-DS-8606A-E I

1

14. Pump Rm. (rm 115) a.

tipi Pmp.-2 b.

CS Pmp.-2 1

1 I

DS-8653 c.

DR Pmp.-2 a

5

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15. Pur.ip Rm. (rm 105) a.

'liPI Pmp.-l b.

CS Pmp.-l 1

1 I

DS-8643 c.

Dil Pmp.-l d.

ECCS Rm. Cir.

16. Dil Clr. it. (rm 113) 1 I

I DS-8654 l

17. CC Pnps. (rm 328)

I 1

I DS-8655 i

I 18.

SW Pmps. (intake structure) 4 4

I DS-863M-D 2

19. Motor Control Centers

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a.

E12E & File (rm 100) 2 1

I DS-9649A & 8 1

1 I

DS-8621D & E 5

b.

EllA (rm 209) l 1

I 05-86211 c.

EllD & F11D (rm 227) a

- + -p' d.

FilC (rm 236) 1 1

I DS-8621F Ell 8 & E11C (rm 304) 1 1

I DS8619 & DS-8631M e.

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Table 3.3-14 (Sheet 3)

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f FIRE DETECTIO:t IllSTRUMEilTS 3

Number flumber Required Type of Detector Tag l

Instrument Location' Installed To be Operable Detectors ilumber j

19. Motor Control Centers (Continued) f.

Li/B (rm 313)

(SEE ITEM 12) q g.

'F12B (rm 319)

(SEE ITEM 13)

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EllE (rm 402) 3 I

I DS-8609A, B & C

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Fil8 (rvi 405) 1 1

f(duct)

DS-8651

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Fila (rm 427) 2 1

I DS-8610A & B k.

F12A, F14 & FIS (rm 428) (SEE ITEM 3)

I 1.

E12A, E14 & E15 (rm 429) (SEE ITEM 7) m.

EF120 (rm 429A) 1 1

I DS-8615D n.

E12C, F12C & EFl2C (SEE ITEM 18) intake structure)

20. Misc. Rooms (safety related. cable

& equip) w2 a.

101, 106 & 109 1

1 I(duct)

DS-8623 u

b.

110,110A, 114 & 126 1

1 I(duct) 05-8622 c.

123, 231, 232 & 241 1

1 I(duct) 0S-8621B

,i d.

124, 234 & 235*

1 1

I(duct)

DS-8621C e.

200, 201A & 203 1

1 I(duct)

DS-86210 f.

208 2

2 I

DS-8621J & K g.

222, 224 & 300 1

1 I(duct)

DS-8652 h.

237 1

1 I

DS-8621H i.

238 1

1 I

DS-8621G j.

240 1

1 I(duct)

DS-8621A k.

303 3

3 I

DS-8608A, B & C 1.

310, 312 & 313 1

1 I(duct)

DS-8619

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314

-2 2

I DS-86080 & DS-8611 3

n.

500 1

1 I(duct)

DS-86268 T

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501 1

1 I(duct)

DS-8626A j

p.

515 1

1 I(duct)

DS-8f;26C i

q.

516 1

1 I(duct)

DS-8626D 7

r.

603 2

2 I

DS-8644E & F

Fire Detectors In high Radiation Areas e

93-j Table 3.3-14 (Sheet 4) f si FIRE DETECTION INSTRUMENTS YA f'

Number Number Required Type of Detector Tag f

Instrument Location Installed To be Operable Detectors Number g.n 21.

EMDG-1 Day Tank (rm 321A) 1 1

FS FS-8702A 22.

EMDG-2 Day Tank (rm 320A) 1 1

FS FS-8702B I-Ionization detector 1(duct) - Inonization detector L:ounted in duct PE - Photelectric detector T - Temperature switch u

3; FS - Flow switch mounted in wet pipe sprinkler system Y's l

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PLANT SYSTEMS, SURVEILLANCE REQUIREMENTS (Continued)

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1.

With a half-life greater than 30 days (excluding Hydrogen

3) and 2.,

In any form other than gas.

b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Snaled sources and fission detectors transferred.without a certi~. !-

cate indicating the last test date shall be tested prior to being placed into use.

c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.8.1.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.

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3/4 7-37

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s PLANT SYSTEMS 3/4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERAT10fl 3.7.9.1 The fire supression water system shall be OPERABLE with; a.

Two high pressure pumps, each with a capacity of 2500 gpm,-

with their discharge aligned to the fire suppression header, b.

Separate water supplies, each with a minimum contained volume of 250,0S0 gallons, and c.

An OPERA 0LE flow path capable of taking suction from the Intake forebay and the Fire Water Storage Tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve head of the water flow alarm device on each sprinkler hose standpipe or spray system riser required to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.3.

a.PPLICABILITY: At all times.

ACTION:

a.

With one puttp and/or one water supply inoperable, restore the f

inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9.1, pre-i pare and subr.it a Special Report to the Commission pursuant to Specification 6.9.2 uithin the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this sytem. The provisions'of Specifications 3.0.3 and 3.0.4 a e not applicable.

b.

With the fire suppression water system otherwise inoperable:

1.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Submit a.Special Report in accordance with Specification 6.9.2; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b)

Confirmed by telecraph, mailgram or facsimile trans-mission no later than the first working day following the event, and TAVIS-BESSE. UNIT 1 3/4 7-38 Amendment No. 9

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PLAtlT SYSTE_ljS I

LIMITIllG CONDITI0tt FOR OPERATI0rl (Continued) l

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c)

In writing within 14 days following the event outlining the action taken, the cause of the inoperability and I

the plans and schedule for restoring the system to OPERABLE status.

SURVEILLAllCE RE0 VIP.EMEilTS 1

I 4.7.9.1.1 The fire suppression water system shall be demonstrated OPERABLE: l a.

At least once per 7 days by verifying the contained water supply volume.

b.

At Icast once per 31 days on a STAGGERED TEST BASIS by starting l

each pump and operating it for at least 15 minutes on recircu-lation flow, At least once per 31 days by verifying that each valve (manual, c.

power operated or automatic) in the flow path that is accessible is in its correct position.

l d.

At least once per 12 months by performance of a system flush.

i e.

At least once per 12 months by cycling each testable valv.e in the flow path through at least one complete cycle of full, travel.

f.

At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system threughout its operating sequence, and:

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Verifying that each automatic valve in the flow path l

acuatcs to its correct position, l

2.

Verifying that each pump develops at least 2375 gpm at a system head of 250 feet, 3.

Cycling each pump valve in the flow path that is not testable during plant ooeration through at least one complete cycle off travel, and 4.

Verifying'that each high pressure pump starts (sequentially) to maintain the. fire suppression water system pressure

< 95 psig.

j DAVIS-BESSE, U; TIT 1 3/4 7-39 Amendment No. 9 i

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PLANT SYSTEMS, SURVEILLANCE RE0VIRU4ENTS (Continued) g.

At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4.7.9.1.2 The fire pump diesel engine shall be demonstrated OPERABLE.

a.

At least once per 31 days by verifying; 1.

The Fire Pump Diesel Day Tank contains at least 300 gallons of fuel, and 2.

The diesel starts from ambient conditions and operates for at least 20 minutes, b.

At least once per 92 days by verifying that a sample of diesel

' fuel from the fuel storage tank, obtained in accordance with AST!!-D270-65, is within the acceptable limits specified in Teble 1 of ASTN 0975-74 when checked for viscosity, water content, and sediment, c.~

At least once per 13 months, during shutdown, by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in cenjuction with its manufacturer's recommendations for the class of service, and 2.

Verifying the diesel starts from ambient conditions on the auto-start signal and operates for t 20 minutes while loaded with the fire pump.

4.7.9.1.3 The fire pump diesel starting 24 volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each cell is above the plates, and

~2.

The.overall battery voltag,e when not cischarging is > 24 "vo l ts.

DAVIS-BESSE. U:n 1

3/4 7-40 Amendment No. 9 i

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1 b.

At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.

c.

At least once per 18 months by verifying that:

1.

The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion naterial.

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l DAVIS-BCSSE, UrlIT I 3/4 7-41 Amendment No. 9

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PLANT SYSTEMS SPRAY AND70R SPRINKLER SYSTEMS LIMITING C0!!DITION FOR OPERATION 3.7.9.2 The following spray and/or sprinkler systems shall be OPERABLE:

a.

Diesel Generator Day Tank Rooms 320A and 321A b.

Diesel Generator Rooms 318 and 319 APPLICABILITY _: Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE.

ACTION:

a.

With one or more of the above requires spray and/or sprinkler systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within I heur; restore the system to OPERABLE status within la i

days or, in lieu of any other repcrt requiced by Specification 6.9.1, prepare and submit a Special Report to the Commission l

pursuant to Specifi:ation 6.9.2 within the next 30 days out-j lining the action taken, the cause of the inoperability and the plans ans schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVIALLANCE RECUIREMENTS 4.7.9.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERAELE:

a.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

b.

At least once per 18 months:

1.

By performing a system functional test which includes

^

simulated automatic actuation of the system, and:

a)

Verifying theat the automatic valves in the flow path actuate to their correct positions on a test signal, and DAVIS-BESSE. UNIT 1 3/4 7-42 Amendment No. 9

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m; PLAtlT SYSTEl:S-SURVEILLAfiCE REQUIREMEllTS (Continued) l b)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2.

By inspcction of each n.ozzle to verify no blockage.

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DAVIS-DESSE, U!IT 1 3/4 7-43 Amendment No..9

s PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 3.7.9.3 The fire ~ hose stations shown in Table 3.7-4 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations in Table 3.7-4 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE Hose station within 1

hour, J

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVIELLAMCE REQUIREMENTS l

4.7.9.3 Each of the fire hose stations shown in Table 3.7-4 shall be demonstrated OPERABLE:

At least once per 31 days by visual inspection of th'e station a.

to assure all required equipment is at the station..

b.

At least once per IS months by:

1.

Removing the hose for insepction and re-racking, and-2.

Replacement of all degraded gaskets in couplings.

c.

At least once per 3 years by:

1.

Partially opening each hose station valve to verify valve OPERASILITY and no ficw blockage.

2.

Conducting 'a hose hydrost,atic test at a pressure at least 50 psig greater than the maximum p. essure available at that hose station.

I DAVIS-BESSE. UMIT 1 3/4 7-44 Amendment No. 9

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_s TABLE 3.7-4 FIRE liOSE STATIONS 1.

HR-4 Turbine Bldg., El. 585, Col. F-9 Secondary Systems Sample Panel 2.

HR-5 Turbine Bldg., El. 585, Col. F-6, Across from TPCW Pumps 3.

HR-11 Turbine Bldg., El. 603, Col. F-5, Near Steam Packing Exhauster 4

HR-12 Turbine Bldg., El. 623, Col. F-9, Outside Control Room 5.

HCS-21 Auxiliary Bldg., El. 565, Col. H-9, Next to MCC F21C 6.

HCS-22 Auxilirry Bldg., El. 565, Col. JF-8.3, Next to Makeup Filters 7.

HCS-23 Auxiliary Bldg., El. 585, Col. H-3, End of Hallway to Diesel Generator Rms 8.

.HCS-24 Auxiliary Bldg., El. 585, Col. H8.2, End of hallway near

. Resin Fill Tank 9.

HCS-25 Auxiliary Bldg., El. 585, Col. JF-9, Hear drumming station 10.

HC3-27 Auxiliary Bldg., El. 603, Col. H-8.2, Beside Hot Lab Door

11. HCS-28 Auxiliary Bldg., El. 603, Col. G-7, Electrical Penetration Room No. 2 12.

HCS-30 Auxiliary Bldg., El. 623, Col. G-4, Containment Purge Exhaust Fan Roem

~ 13.

HCS-31 Auxiliary Bldg., El. 638, Col. F-9, Control Room A/C Equip. Rm next to MCCE23B 14 HCS-32-Auxiliary Bldg., El. 555, Col. G-7, Walkway to ECCS Room No. 2

15. HCS-33 Auxiliary Bldg., El. 555, Col. H-8, Walkway to ECCS Room No. 1 DAVIS-BESSE, UNIT 1 3/4 7-45 Amendment No. 9 4

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m TABLE 3.7-4 (Continued) 16.

HCS-34 Auxiliary Bldg., El. 565,' Col. G-10, Between Elevator and Degasifier 17.

HCS-35 Auxiliary Bldg., El. 565, Col. J-8,5, Beside BWST Heat ~~

exchanger 18.

HCS-36 Auxiliary Bldg., El. 585, Col. H-8, Mechanical Penetration Room No. 4

19. HCS-38 Auxiliary Bldg., El. 585, Col. JE-7, Mechanical Penetration Room No. 3 20.

HCS-39 Auxiliary Bldg., El. 603, Col. JD2-7.7. Electrical Penetration Room No. I 21.

HCS-41 Auxiliary Bldg., El. 643, Col. K-7.35, Main Steam Line Room No. 1 22.

HCS-42 Auxiliary Bldg., El. 623, Col. K-9, Near Fuel Handling Area Exhaust Fan-

23. HCS-43 Auxiliary Bldg., El. 638, Col. G-8.6, Control Room A/C Equip. Rm.. NW corner

24. HCS-44 Auxiliary Bldg., El. 623, Col. G-8, Outside Control Room Emergency Exit Door

25. HRN-16 Auxiliary Bldg., El. 613,. C01. F-10.1, Stairwell next to Cable Spreading Room

26. HRN-17 Auxiliary Bldg., El. 623, Col. F-9.3, Stairwell next to Control Rocm

27. HRN-20 Auxiliary Bldg., El. 603, Col. F-9.3, Stairwell below Cable Spreading Rocm i

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DAVIS-BESSE, UNIT 1 3/4 7-46 Amendment No. 9

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l PLANT SYSTEMS.

3/4.7.10 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.10 All penetration fire barriers protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

a.

With one or r. ore of the above required penetration fire barriers non-functional, establish a continuous fire watch on at least one side of the affected penetration within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

.b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RECUIREMENTS i

4.7.10 The above required penetration fire barriers shall be verified to be functional:

a.

At least cnce per 18 months by a visual inspection.

b.

Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

i OAVIS-BESSF, UNIT l_

3/4 7-47 Amendment No. 9

p 3/4.3 INSTRUMENTATION i

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BASES

-i REMOTE SNUTDOWN INSTRUMENTATION (Continued)

HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the_ event control room habitability is i

lost.

I 3/4.- 3. 3. 6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that suffi-l cient information is available on selected plant parameters to monitor and assess these variables following an accident.

4 3/4.3.3.7 CHLORINE OETECTION SYSTEMS The OPERABILITY of'the chlorine detection systems ensures that an acci-dental chlorine release will be detected pecmptly and the control room emergency ventilation system will automatically isolate the control room and initiate its operation in the recirculation mode to provide the required p'rotection. The chlorine detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.9L, " Protection of Nuclear Power Plant Control Room Operations i

Against an Accidental Chlorine Release," February 1975.

3/4.3.3.8 FIRE DETECTION INSTRUMENTATION Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

i This capability is required in order to detect and locate fires in i

their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the i

j overall facility fire protection program.

[

I.

In the event that a portion of the fire detection instrumentation is 4

inoperable, the establishment of frecuent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

DAVIS-GESSE 40 NIT 1 B 3/4 3-3 Amendment No. 9 c.

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PLANT SYSTEMS BASES 3/4.7.7 HYDRAULIC S!!UUBERS The hydraulic snubbers are required OPERABLE to' ensure that the structural integrity of the reactcr coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. The only snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety related system.

The inspection frequency applicable to snubbers containing seals fabricated from materials which have been demonstrated compatible with their operating environment is based upon maintaining a constant level of snubber protection. Therefore, the required inspection interval varies inversely with the observed snubber failures. The number cf inoperable snubbers found during an inspection of these snubbers deter-mines the time interval for the next required inspection of these snubbers.

Inspections performed before that interval has elapsed may be used as a new reference point to detennine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 255) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

To provide further assurance of snubber reliability, a representa-tive sample of the installed snubbers will be functionally tested during plant shutdcc.ns at 18 month intervals.

These tests will include stroking of the snubbers to verify proper piston movement, lock-up and bleed.

Observed failures of these sample snubbers will require functional testing of additional units. To minimize personnel exposures, snubbers installed in high radiation zones or in especially difficult to remove locations may be exempted from these functional testing requirements provided the OPERACILITY of these snubbers was demonstrated during functional testing at either the comoletion of their fabrication or at a subsequent date.

DAVIS-BESSE Ui;IT 1 B 3/4 7-5

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6 PLANT SYSTEMS i

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3/4.7.8 SEALED SOURCE CONTAININATION The limitations on removable contamination for sources requiring leak testini), including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium..This limitation will ensure that leakage from by product, source, and special nuclear material sources will not exceed' allowable' intake values.

3/4.7.9 FIRE SUPPRES3 ION SYSTEMS _

The OPERABILITY of the fire suppression systems ensures that adequate l

+

fire suppression caoability is available to confine and extinguish fires i

occuring in any portion of the facility where safety related equipment is located.

The fire suppression system consists of the water system, spray and/or sprinklers, and fire hose stations.

The collective capability of the fire suppression systems is adequate to minimize potential dameJe to safety related equipment and is a major element in i

the facility fire protection program.

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

4 In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides-the major fire ' suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evalua-tion of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

3/4.7.10 PENETRATION FIRE EARRIERS l

The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

This design feature minimi:es the possibility of a singic fire rapidly involving several areas of the facility prior to detection and extinguishment.

The penetration fire

. barriers are a passive element in the facility fire protection program and are. subject to periodic inspections 4 During periods of -tina when the barriers are not functional, a cen-tinuous fire watch is required to oc maintainad in the vicinity of the l-affected barrier until the. barrier is restored to functional status.

1 CAVIS-CESSF, UNIT 1 8 3/4 7-6 Amendment No. 9

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6.0 ADMINISTRATIVE C0flTROLS 6.1 RESP 0flSIBillTY

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6.1.1 The (Plant Superintendent) shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION OFFSITE_

6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shif t shall be compcsed of at least the minimum shif t crew composition'shown in Table 6.2-1.

b.

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

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

d.

An individual qualified in radiation prctection procedures shall be on site when fuel is in the reactor..

e.

All COPE ALTERATI0!:S shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi-bilities during this operation.

I f.

A Fire Brigade of at least 3 mcmbers shall be maintained onsite at all tir:es. The Fire Brigade shall not include the minimum shif t cr ew shown in-Table 6.2-1 or any personnel required for other r" ntial functions during a fire emergency.

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DMIS GESSE, Ut:f f 1 6-3 Amendment tio. 9

TABLE 6.2-1 MIlllMUM SHIFT CREW COMPOSITIOil#

4 LICENSE APPLICABLE MODES CATEGORY l, 2, 3 & 4 5&6 S0L 1

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1 4

tion-Licensed 2

1 4

0oes not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling supervising CORE ALTERATIONS.

t

Shift crew composition may be less than the minimum requirements for a pe iod of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acccmmodate unexcected abe ace of on duty shif t crew members provided inmediate action is taken to restore the shif t crew composition to within the minimum requirements of Table 6.2-1.

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J ADMIllISTRATIVE C0!!TROLS 6.3 FACILITY STAFF QUALIFICATI0 TIS

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6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of-AilSI Ill8.1-1971 for comparable positions, except for the (Radiation Protection Manager) who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.

6.4 TRAltllt!G 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and recommendations of Section 5.5 of AflSI Ill8.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Bridage shall be maintained under the direction of the Fire Marshall and shall meet or exceed the requirements of Section 27 of the NFPA Codo-1976.

6.5 REVIEW AtlD AUDIT 6.5.1 - STATI0fl REVIEU C0ARD (SRB)

FUilCTIO!1 -

6.5.1.1 The Station Review Board (SRB) shall function to advise the Station Superintendent on all matters related to nuclear safety.

mn 9

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L DAVIS-RESSr. Ui!IT.1 6-5 Amendment No. 9

ADMIflISTRATIVE C0'lTROLS COMPOSITI0tj 6.5.1.2 The Station Review Board shall be composed of the:

Chairman:

Station Superintendent Member:

Operations Engineer Member:

Technical Engineer Member:

Mainta-nce Engineer Member:

Instr

.nt and Control Engineer Member:

.Nucls and Performance Engineer Member:

Chemist and Health Physicist Member:

Reliability Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed 'in writing by the SRB Chairman to serve on a temporary basis; however, no more than two

?

alternates shall participate as voting memoers in SRB activities at any one tirre.

l.

MEETING FREOUENCY l

6.5.1.4 The SRB shall meet at least once per calendar month and as.

convened by the SRB Chairman or his designated alternate.

QUORUM

5. 5.1. 5 A quorum of' the SRS shall consist of the Chairman or his

]

designated alternate and four members including alternates.

RESPONSIBILITIES _

6.5.1.6 The Station Review 8 card shall be responsible for:

a.

Review of 1) all proccdures required by Soecification 6.8 and changes thereto, 2) any otner proposed procedures or changes thereto as determined by the Station Superintendent to affect nuclear safety, b.

Review of all proposed tests and experiments ' hat affect t

nuclear safety.

QoI DAVIS-CESSr. Hi!r 1 6-6' L db)

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AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the CilRB.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the entire

- station staff at least once per 12 months.

The results of actions tal:en to correct deficiencies c.

occurring in unit equipment, structurcs, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Quality 4

Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e._

The Station Emergency Plan and implementing procedures at least once per 24 months.

i f.

The Station Security Plan and implementing procedures at least once per 24 months.

g.

Any other area of facility operation considered appropriate by the CimB.

4 h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months.

-1.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee per-sonnel or cn outside fire protection firm.

j.

An inspection and audit of the fire protection and loss pre-vention program shall be performed by a qualified outside fire consulant at least once per 36 months.

i AUTil0RITY 6.5.2.9 The Company !!uclear Review Board shall report to and advise the Senior Vice President, Operations on t53se areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.3.

DAVIS-GESSC, UilIT I 6-11 Amendment No. 9

~.

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10. Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of each CNRB meeting shall be prepared, approved i

and forwarded to the Senior Vice President, Operations and CNRB members within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice Presi-

-dent, Operations and CNRS members within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President, Operations and CNRB members and to the canagement positions responsible for the areas audited within 30 days after completion of tne audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The follouing actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months notification to the Commission shall be reviewed by the SRB and submitted to the CURB.

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l DAVIS-BESSE, UNIT 1 6-12

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_a lACMIllISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour.

b.

The Safety Limit violation shall be reported to the Commission, the Vice President, Energy Supply and to the CNRS within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SRF3.

This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Cnmmission, the CNRB and the Vice President, Energy Supply within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced belcw:

a.

The applicable procedures reccmmended in Appendix "A" of Regulatory Guide 1.33, llovember,1972.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation, f;

Fire Protection Program implementation.

~~'

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the SRB and approved by the Station Superintendent prior to irrplementation and reviewed periodically as set forth in administrative procedures.

DAVIS-BESSE, UNIT 1 6-13 Amdndment fio. 9 l

ADi4IllISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of the original procedure is not altered.

a.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

The change is documented, reviewed by the SRB and approved c.

by the Station Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREl!ENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 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 Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant start'up and power escalation testing shall be submitted following (1) receipt of an operating license, (2) cmendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant. The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditicns or characteristics obtained during tne test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were rcquired to obtain satisfactory operation shall also'be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.

6.9.1.2 Startup reports shall be subnitted within (1) 90 days following completion of the startup test program, (2) 90 days followine resumption or commencement of cenmerical power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does g.

not cover all three events (i.e., initial criticality, ccmpletion of startup test program, and resunption or conmencement of commercial 00"O-f D

DAVIS-BESSEE, UNIT 1 6-14 o o 1i t-

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occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

Reattor protection system or engineered safety feature instru-a.

ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems, b.

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limitin: condition for operation.

c.

Observed inadequacies in the impicmentation of administrative or procedural controis which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d.

Abnormal aegradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting frem the fission process.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time perico specified for each report.

These reports shall be submitted covering the activitie identified belcw pursuant to the requirements of the ap-plicable refeience specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Ino"rable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

Inoperable Meteorological Monitoring Instrumentation, Specifi-c.

cation 3.3.3.4 d.

Fire detection instrumentation. Specification 3.3.3.8.

Fire suppression systems, Specifications 3.7;9.1 and e.

3.7.9.2.

DAVIS-CESSE, UNIT i 6-19 Amendment,No. 9

~

ADMIllISTRATIVE C0flTROLS 6.9 REPORTIi!G REOUIREMENTS (Continued) f.

Seismic event analysis, Specification 4.3.3.3.2.

6.10 RECOD.D_ RETEi!TI0ti 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval a.

at each power level, b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.

ALL REPORTABLE OCCURREllCES submitted to the Ccmmission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specificaticns, Records of changes cade to Operating Precc;:ures, e.

f.

Records of radioactive shipments.

g.

Records of sealed source aad fission detector leak tests and results.

.h.

Records of annual physical inventory or all sealed source material of record, 1

6.10.2 The folloiting records shall be retained for the duration of the' Facility Operating Lictnse:

Records and drawing changes reflecting facility design r difi-a.

cations mede to systems and c;uipment described in the Final Safety Analysis Report, b.

Records of new 6nd irradiated f' il inventory, fuel transfers and assemoly burnup nistories.

Records of radiation exposure for all individu:ls entering c.

radia tion control areas.

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3 DAVIS-BESSE, U:!IT I

~ 6-20 Amencment No. 9

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