ML19308A817

Proposed Tech Specs 3,4,5 & 6 Re Fire Protection & Detection Sys

ML19308A817
Person / Time
Site:	Oconee
Issue date:	11/25/1977
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19308A816	List: ML19308A815 ML19308A817 ML19308A819
References
NUDOCS 7912120607
Download: ML19308A817 (17)

Text

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3.4 STEni AxD 10tER CO:uERSIO:. SYSTIa 3.4-1 3.5 INSTRUMDGATION SYSTDiS 3.5-1 3.5.1 Operational s..fet Instru-entation

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3.5-1 3.5.2 Control Rod C'roup and Poteer Distribution Lir.its' 3.5-6 3.5.3 Engineered Sifetv Features Protective System 3.5-25 Actuation Setnoints 3.5.4 Incore instre-ontorion 3.5-27 3.6 REACTOR SUILDING 3.6-1 3.7 AUXILIARY ELECTRICAL SYSTDiS

.3.7-1 3.8 FUEL LOADING A O REFUELING 3.0-1 3.9

. RELEASE OF LIQ"1D RADIOACTIVE WASTE 3.9-1 3.10 RELEASE OF GASEOUS RADICACTIVE WASTE 3.10-1 3.11 MAXI!K'.i POUER RESTRICTIONS 3.11-1 3.12 REACTOR EUILDING POLAR CMNE AND AUXILIARY !!OIST 3.12-1 3.13 SECO::Dl.RY SYST!. ACTIVITY 3.13-1 3.14 SHOCK SUPPRESSORS (SNUBBERS) 3.14-1 3.15 PENETRATION ROOM VENTILATION SYSTEMS 3.15-1 3.16 HYOR0 GEN PURGE SYSTEM 3.17 FIRE PROTECTION AND DETECTION SYSTEMS 3.17-1 4

. SUnvt11.1. Ante PaotixE":: TS 4_1 4.0 SURVEILLANCE STANDARDS 4.1-1

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4.1 OPERAT70NAL SAFETY REVIEW 4.1-1 4.2 REACTOR CCOIJ.'G SYSTDi SURVEILLANCE 4.2-1 4.3 TESTING FOLLOUING OPENING OF SYSTDI 4.3-1 4.4 REACTOR LUILDING 4.4-1

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Section P'ne

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~J DESIGN FEATURES 5.1-1 5

5.1 SITE 5.1-1 5.2 CONIAINMENT 5.2-1 5.3-1 5.3 REACTOR 5.4' NEW AND SPENT FUEL STORAGE FACILITIES 5.4-1 6.1-1 6

ADMINISTRATIVE CONTROLS

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6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1-1 6.1.1 Organization 6.1-1 6.1.2 Review and Audit 6.1-2,

6.2 ACTION TO BE TAKEN IN THE EVENT OF AN INCIDENT 6.2-1 26/21/13 REPCRTABLE TO THE COMMISSION 6.3 ACTION TO BE TAKEN IN THE EVE' T A SAFETY LD11T IS EXCEEDED 6.3-1 6.4 STATION OPE?.ATING PROCEDURES 6.4-1 6.5 STATION OPEMTINO RECORDS 6.5-1 6.6 STATION REPORTII:G REQUIRCIENIS 6.6-1 6.6.1 Routine Reports 6.6-1 6.6.2 Non-Routine Recorts 6.6-6 6.6.3 Special Reoort2 6.6-9 6.7 RADIOLOGICAL CO:IMOLS 6.7-1 e

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Section h

4. 4.1.

Conen Jne.ent Leckace Tests 4.4-1 f.4-6 4.4.2 Structural Intecrity 4.4.3 Hydrogen Purce Svsten 4.4-10 4.5 DIERGENCY CORE CCOLING SYSTDIS AND REACTOR SUILDING 4.5-1 COOLING SYSTE:S PERIODIC TESTING 4.5.1 Emerneney Core Coelinc: Sy s t e-.s 4.5-1 4.5.2 Reactor Building Cooling Systems

4. 5-6 4.5-10

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4.5.3 Penetration Room Ventilation System 4.5.4 Low Pressure Iniection System Leakaxe 4.5 12 4.6 EMERGENCY POWER SYSTDi PERIODIC TESTING 4.6-1 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4.7-1 i

4.7.1 Control Rod Drive' System Functional Tests 4.7-1 l

4.7.2 Control Rod Program Verification 4.7-2 4.8 MAIN STEAM STOP VALVES 4.8-1 4.9 DfERGENCY FEEDWATER PUMP PERIODIC TESTING 4.9-1 4.10 REACTIVITY ANOMALIES 4.10-1 4.11 ENVIRONMENTAL SURVEILLANCE 4.11-1 4.12 CONTROL ROOM'PILTERING SYST1!M t.12-1 4.13 FUEL SURVEILLANCE 4.13-1 4.14 REACTOR BUILDING PURGE FILTERING SYSTEM 4.14-1 4.15 IODINE RADIATION !ONITORING FILTERS

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4.15-1 4.16 RADI0 ACTIVE MATERIALS SOURCES 4.16-1 4.18 HYDRAULIC SHOCK SUPPRESSORS,(SNUBBERS) 4.18-1 4.19 FIRE PROTECTION AND DETECTION SYSTEM 4,1g_1 i

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3.17 FIRE PROTECTION AND DETECTION SYSTEMS Applicability This specification applies to the operability of fire protection and detection systems which protect systems and equipment required for safe shutdown.

Objective To assure the operability of fire protection and detection system Specification 3.17.1 The minimum fire detection instrumentation for each fire detection

one shown in Table 3.17-1 shall be operable. When this specification is determined not to be met, appropriate action shall be taken consisting of one or more of the following:

1.

Within I hour, a fire watch patrol shall be established to inspect

• an accessible zone with the inoperable instrumentation at least once per hour.

2 The inoperable instrumentation'shall be restored to operable status within 14 days or a r'eport shall be submitted to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrumentation to operable status.

a 3.17.2 Two high pressure service water pumps with a capacity of 6000 gpm each and with automatic initiation logic shall be operable and aligned to the high pressure fire header. When this specification is determined not to be met, appropriate action shall be taken consisting of the following:

i 1.

The inoperable equipment shall be restored to operable status j

within 7 days or a report shall be submitted to the Commission within the next 30 days outlining the plans and procedu~res to be J

j used to provide for the loss of redundancy in this system.

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2.

With no Fire Suppression Water System operabic, in 13tu of the above, the following action shall be taken.

a)

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a backup Fire Suppression Water System shall be established, im b) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the Commission shall be notified by telephone, and in writing no later than the first working day following the

event, c)

Within 14 days of the event, a report shall be submitted to the Commission outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the syste' to operable status.

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3.17.3 The sprinkler systens in safety related areas listed in Table 3.17-1

.g shall be operable.

If a system is determined to be inoperable, the 1

following corrective action shall be taken.

1.

A continuous fire' watch with backup fire suppression equipment shall be established in the area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.

The sprinkler system shall be restored to operable status within 14 days or a report shall be submitted to the Ccamis-sion within the next 30 days outlining the cause of inoper-ability and the plans for restoring the system to operable status.

3.17.4 The fire hose stations listed in Table 3.1,7-1 shall be operable or additional equivalent capacity hoses shall be provided at an operable hose station within one hour such that the additional hoses can be readily connected to the operable station and extended into the unprotected area if the need arises.

3.17.5 When a penetration fire barrier protecting a safety related area is determined to be non-functional, a continuous fire watch shall be established on at least one side of the affected penetration within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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TABLE 3.17-1 A.

Fire Detection Instrumentation DETECTORS ELEV UNIT EQUIPMENT / LOCATION PROTECTED PROVIDED/0PERABLE 771+0 1-2 Motor Control Centers 3/2 3

Motor Control Centers 2/1 775+0 1

Emer FW Pump 1/1 2

Emer FW Pump 1/1 3

Emer FW Pump 1/1 796+6 1

Reactor Bldg Penetrations 4/4 RCP's 4/4 RBCU 3/2 2

Same as Unit 1 3

Same as Unit i 1-2 Equipment Room 12/6 3

Equipment Room 5/3

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1 Load Centers, Switchgear 11/6 2

Same as Unit 1 3

Load Centers, Switchgear 8/4 1-2 Switchgear, Transformer 4/2 3

Switchgear 3/2 809&3 1

Battery Room 2/1

Motor Control Centers 3/2 1-2 Cable Spread Room 8/4 2

Battery Room 2/1 Motor Control Centers 3/2 3

Battery Room 2/1 Motor Control Centers 3/2 3

Cable Spread Room 6/3 822+0 1-2 Control Room 4/2 1

Penetration Room 4/4 1

Cable Shaft 1/1 l

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. TABLE 3.17-1 (cont.)

DETECTORS ELEY UNIT EQUIPMENT / LOCATION PROTECTED PROVIDED/0PERABLE l(

4/4 2

Penetration Room 2/1 2

Cable Shaf e 3/2 3

Control Room 3

Penetration Room 4/4 1/1 3

Cable Shafc B.

Sprinkler System _s Emergency FDWIit Pump Units 1, 2 and 3

' Transformers CT-1 CT-2 I

CT-3

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CT-4 CT-5

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C.

Fire Hose Stations ELEV 771+0 HOSE STATION NO.

Hose Station (Turbine Building)

AX-1 TB 1-B-19 TB 3-D-28 TB 1-D-28 TB 3-D-43 AX-2 TB 1-D-39 TB 3-F-42 TB 1-D-45 TB 3-J-23 AX-3 TB 1-D-53 TB 3-J-28 TB 1-F-43 TB 3-J-32 AX-4 TB 1-J-23 TB 3-J-40 TB 1-J-28 TB 3-J-47

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AX-5 TB 1-J-32 TB 3-M-24 TB 1-J-43 TB 3-M-29 ELEV 783+9 TB 1-J-47 TB 3-M-30 TB 1-M-24 TB 3-H-39 AX-6 TB 1-M-29 TB 3-M-43 TB 1-M-31 AK-7 TB 1-M-43 TB 5-M-24 TB 5-M-31 AK-8 TB 5-M-42 AX-9 AI-10

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AX-ll 3.17-4

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I BhSES Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to d,etect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

The operability of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring 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 damage to safety related equipment and is a major element in the fscility fire protection program.

f 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.

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 evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the nuclear plant.

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

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of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the j

facility fire protec, tion program and are subject to periodic inspections.

s During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier i,s restored to functional status.

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4.19 FIRE PROTECTION AND 7ETECTION SYSTEM Applicabil_ity Applies to the fire protection and detection systems which protect systems and equipment required for safe shutdown.

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Objective To verify the operability of fire protection and detection systems.

Specifications 4.19.1 'Ihe High Pressure Fire Protection System components shall be tested as follows:

Item Frequency (a)

High pressure service water pump Monthly functional test (b) System functional test Every 18 months (c) High pressure service water pump Annually capacity test to verify flow of 3000 gpm (d) System Flow Test in Accordance with Every 3 years Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, NFPA

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(e)

Alignment of fire protection valves Monthly (f)

Cycling each valve in the flow path that Every 18 months is not testable during plant operation through at least one complete cycle of full travel (g)

Sprinkler systems in safety related areas 1.

System functional test Annually 2.

Inspection of spray headers Annually 3.

Inspection of spray nozzle Annually (h)

Fire hose stations 1.

Visual inspection Monthly 2.

Maintenance inspection Annually 3.

Partial opening of fire hose Every 3 year',

station valve 4.

Hose Hydrostatic test at least Every 3 years 50 psig greater than the l

maximum pressure at the l

station 4.19-1

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4'.19.2 ' 1he fire detection system shall be tested for operability as follows:

Item Frequency

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(a)

Operability of detectors Semi-Annually (b)

Operability of annunciators Seni-Annually 4.19.3 Penetration fire barriers protecting safety-related areas shall be verified functional by visual inspection at least once per 18 months and prior to declaring a penetration fire barrier functional following repairs or maintenance.

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.6.0 ADMINISTRATIVE CONT 01,5

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6.1 ORGANIZATION, REVIEW, AND AtJDIT 6.1.1

- Organization 6.1.1.1 The station Hansger shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

l 6.1.1.2 In all matters pertaining to actual operation and maintenance and to these Technical Specifications, the station Manager shall report to and be directly responsible to the Vice President, Steam Production, through the Hanager, Nuclear Production. The organization is shown in Figure 6.1-2.

6.1.1.3 The station organization for Operations. Technical Services and Maintenance shall be functionally as shown in Figure 6.1-1.

Minimum operating shift requirements are s'pecified in Table 6.1-1.

6.1.1.4 Incorporated in the staff of the' station shall be personnel meeting the minimum requirements encompassing the training i,

and experience described in Section 4 of the ANSI N18.1-1971,

" Selection and Training of Nuclear Power Plant Personnel."

'6.1.1.5 kettsining and replacement of station personnel shall be in

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accordance with Sectica,5.5 of the ANSI N18.1-1971, " Selection and Trsining of Nuclear Power Plant Personnel."

6.1.1.6 A training program for che fire brigade shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.

6.1.2 Technical Review and Control 6.1.2.1 Activities a.

Procedures required by Technical Specification 6.4 and other procedures which affeet station nucicar safety, and changes (other than editorial or typographical changes) thereto, shall be prepared by a qualified individual /

organi:ation.

Each such procedure', or procedure. chang ~e, shall be reviewed by an individual / group other than the individual / group whien prepared the procedure, or procedure change, but who may be from the same organization as the individual / group which prepared the procedure, or procedure change.

Such procedures and procedure changes may be approved for temporsry use by two miembers of the station staff, at least one of when holds a Senior Reactor Operacor's License nn the unit (s) affected.

Procedures and procedure changes shall be approved prior to use or within seven days, of receiving temporary approv-ai for use by the station'Hanager; ur by the Operattnr. Superintendent, the Technical Servlees Superintendctu or the Hsintenance Superintendent, as previously designated by the station Manager.

b.

Proposed changes to the Technical Specifications shall be prepared by a k

qualified individual /organi:ation.

The preparation of each proposed Tech-nical Specificatluns change shall be reviewed by an individuai/ group other l

than the individual /(,roup which prepared the proposed change, but who may l

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'Oh/tochhichpreparedthe be from the same organization as the individu

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Proposed changes to the Technical Specifications shall proposed change.

be approved by the 8tation Manager.

I to station nuclent safety-reinted structuren.

Proposcil mod! Cleat lons s.

nystema and component a sha11 he desir,ned by a qualIfled individual /

F.ach such modification shall be reviewed by an individual /

organizntion.

group other t.han the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modiffcation.

Proposed modifications to station nuclear safety-related structures, systems and components shall be approved prior to implementation by the station Manager; or by the Operating Superintendent, the Technical Services Superintendent, or the Maintenance Superintendent, as previously designated by the station Manager.

Individuals responsible for reviews performed in accordance with 6.1.2.1.a, d.

6.1.2.1.b. and 6.1.2.1.c shall be members of the station supervisory staff, previously designated by the station Manager to perform Each such review shall include a determination of whether such reviews.

If deemed or not additional, cross-disciplinary, review is necessary.

necessary, such review shall be performed by the appropriate designated station review personnel.

Proposed tests and experiments which affect station nuclear safety and are e.

not addressed in the FSAR or Technical Specifications shall be reviewed by the station Manager; or by the Operating Superintendent, the Technical Servi-(

ces Superintendent or the Maintenance Superintendent, as previously desig-nated by the station Manager.

f.

Incidents reportable pursuant to Technical Specification 6.6.2.1 and vio-lacions of Technical Specifications shall be investigated and a report pre-pared which evaluates the occurrence and which provides recommendations to prevent recurrence.

Such reports shall be approved by the station Manager and transmitted to the Vice President, Steam Production, or his designee; and to the Director of the Nuclear Saf ety Review Board.

The station Manager shall assure the performance of special reviews and g.

investigations, and the preparation and subm'.ttal of reports thereon, as requested by the Vice Presioent, Scear Production.

h.

The station security program, and implementing procedures, shall be reviewed at least annually.

Changes determined to be necessary as a result of such review shall be approved by the station Manager and trans-mitted to the Vice President, Steam Production, or his designee ard to the Dirsceor of the Ituelear Saf ety Review Board.

1.

The station emergency plan, and implementing procedures, shall be reviewed at least annually.

Changes decernined to be necessary as a result of such revieu shall be approved by the station Manager and trans-mitted to the Vice President, Steam Production, or his designee; and to the Director of the liuclear Safety Review Board.

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j. The station manager shall assure that an independent fire pro-tection and loss prevention inspection and audit shall be per-f ermed annually utilizing qualified off-site personnel and that shall be an inspection and audic by a qualified fire consultant nerformed at intervals no greater than three years.

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q Any cther crea of ct tien operation consid red cyprcpriato by th3 NSRB 3

or the Vice President, Sted Production.

The station fire protection program and implementing procedures at least' h.

once per 2Amonths.

6.1.3.5 Responsibilities and Authorities The HSRB shall report to and advise the Vice President, Steam Production a.

on those areas of responsibility specified in Specifications 6.1.3.3 and 6.1.3.4.

Minutes shall be prepared and forwarded to the Vice President, Steam b.

Production, and to the Senior Vice President, Production and Transmission, within 14 days following each formal meeting of the NSRB.

Records of activities performed-in accordance with Specifications 6.1.3.3 c.

i and 6.1.3.4 shall be maintained.

d.. Audit reports encompassed by Section 6.1.3.4 shall be forwarded to the Vice President, Steam Production, and to the Senior Vice President, Pro-duction and Transmissiou and to the management positions respcnsible for the areas audited within 30 days o' completion of each audit.

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TABLE 6.1-1 Mia N = operettas shift Requiremente With Fuel in the h ee" Reactor Veseele Unit 1 or 2 Above Dalto 1 and 2 Above Dmite 1 or 2 Above Unita 1 and 2 Cold Unite 1, 2 Dette 1, 2 Minimum AEC Cold shutJoung Unit Cold h tdeung Unit Cold htdemas Unit Shutdowel Wait 3 and 3 Above and 3 Cold License seestrumente 1 Cold h edous 3 Cold h edous 3 Above cold sheedeue Above Cold shutdese Cold h tdeus h temme seater Reactor Operator 2

2 2

2 3

2 s

i Beactor operater 4

4 4

4 4

3 Walicemoed operator 2

2 2

2 4*

Additiemal Requiremente 1.

One licensed operator per unit shall be in the Control Room et all time when there le fuel la the reactor vessel.

2.

hoo licensed operatore shall be la the Control Room durirg startup med scheduled shutdown of a reactor.

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3.

At least one licensed operator skall be la the reactor building when fuel bandling operatione se the reacter bu11 dias are la progrees.

4.

As operator holding a senior Reactor Operator license and seeigned no other operettomal dettee shall be in direct charge of refueling operatione.

3.

At least one persea per ehtf t shell have sufficleat training to perform routtaa health physica i

requirseente.

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If the computer for a reactor le inoperable for more thea sight hours, an operator in addition

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to those required above shall supplement the shif t crew.

M 7.

A fire brigade of 5 membere shell be malatained on este at 11 times, nie esclude. 3 member.

of the mialmum operating oblf t requirements that are required to be present in the control rooms.

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STATION OPERATING PROCEDUKES

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6.4 Specf.fication The station shall be operated and maintained in accordance with Written procedures with appropriate

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6.4.1 approved procedures.

check-of f lists and instructions shall be provided for the folloving conditions:

Normal startup, operation and shutdown of the completc facility and of all systems and components involving nuclear a.

safety of the facility.

b.

Refueling operations.

specific and foreseen potential Actions taken to correct c.

malfunctions of systems or components involving nuclear safety and radiation levels, including. responses to alarms, suspected primary systa= leaks and abnormal reactivity changes, Emergency procedures involving potential or actual reicaqe d.

of radioactivity.

Preventive or corrective maintenance which could affect

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nuclear safety pr radiation exposure to personnel.

f.- Station survey following an earthquake.

Radiation control procedures.

g.

h.

Operstion of radioactive waste management systems.

Contral of pH in recirculated coolant after loss-of-coolant 1.

Procedure shall state that pH will be measured and the accident.

addition of appropriate caustic to coolant will co=mence within 30 minutes after switchover to recirculation mode of core cooling to adjust the p!! to a range of 7.0 to 8.0 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

j. Nuclear safety-related periodic test procedures.

Procedures shall in-k.

Long-term energency core cooling systems.

clude provision for remote or local operation of system components necessary to establish low pressure injection within 15 minutes

' after a line break..

1.

Tire Protection Program implementation Quarterly selected drills shall be conducted on site emergency 6.4.2 procedures including assembly preparatory to evacuation off site and a check of the adequacy of communications with off-site.

support groups.

A respiratory protective program approved by the Commission shall be 6.4.3 in force.

6.4-1

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9 Senior Vice President Production and Transmicsion

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Vice President Nuclear Safety Steam Production Review Board Manager Nuclear Production Manapr Oconee Nuclear Station

. Responsible for Fire Protection Program

) OCONEE NUCLEAR STATION MANAGEMENT ORGANIZATION CHART Figure 6.1-2 6.1-8 3

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Manager Oconee Nuclear Station

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I Administrative Technical Services Superintendent Superintendent Operating Maintenance

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Services Superinitendent Superintendent gno itation Safety Performance Operating Mechanical Supervisor Engineer Engineer Maintenance 4 (Fire i rotect,on) t Rnnorvisnr SRO Enylneer Site llealth Shift Instrument and Physicist Supervisors Electricul SRO Engineer Y

Chemist Shift Personnel R#

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M m irowse OCONEE NUCLEAR STATION l

NY STATION ORGANIZATION CHART

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FIGURE 6.1-1

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