ML19312B893

Proposed Revisions to Tech Specs 3.17,4.19 & 6.1 Re Fire Protection & Detection Sys

ML19312B893
Person / Time
Site:	Oconee
Issue date:	07/18/1977
From:	DUKE POWER CO.
To:
Shared Package
ML19312B889	List: ML19312B888 ML19312B893
References
NUDOCS 7911250081
Download: ML19312B893 (9)

Text

,

. ~

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

Objective To assure the operability of fire protection and detection systems when the reactor is in conditions above cold shutdown.

Specification 3.17.1 The minimum fire detection instrumentation for each fire detection zone shown in Table 3.17-1 shall be operable. When this specifica-tion is determined not to be met, appropriate action shall be taken consisting of one or more of the following:

1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a fire watch patrol shall be established to in-spect 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 report shall be submitted to the Com-mission within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to operable status.

3.17.2 Two high pressure service water pumps 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;

1. The inoperable equipment shall be restored to operable status within 7 days or a report shall be submitted to the Commission within the next 10 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

2. With no Fire Suppression Water System operable, in lieu 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, 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 outlining the actions taken and the plans and schedule for' restoring the system to operable status, c) The Fire Suppression Water System shall be restored to operable status within 14 days or a report shall be submitted to the Commission within the next 10 days outlining the cause of the malfunction and the plans for restoring the system to operable status.

O b ?L We 6 0 D \

3.17-1

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

. . shall be operable. If a system is determined to be inoperable, the 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 Commis-sion within the next 10 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 3.17-1 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 />.

l, I

Y 97 l

l 3.17-2

. _. _ , _ .,_ _ _..-_., _ _ ._~ __- . _

s 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 1 1-2 Equipment Room 12/6 3 Equipment Room 5/3 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 Sp ead 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 Shaf t 1/1 1 17_1

TABLE 3.17-1 (cont.

DETECTORS UNIT EQUIPMENT / LOCATION PROTECTED PROVIDED/ OPERABLE ELEV 2 Penetration Room 4/4 2 Cable Shaft 2/1 3 Control Room 3/2 3 Penetration Room 4/4 3 Cable Shaf t 1/1 1 B. Sprfnkler Systems Emergency FDWIR Pump Units 1, 2 and 3 Transformers CT-1 CT-2 CT-3 CT-4 CT-5 C. Fire Hose Stations ELEV 771+0 HOSE STATION NO.

AX-1 AX-2 AX-3 AX-4 AX-!

ELEV 783+9 AX-6 AX-7

' AX-8 AX-9 i

i

' AX-10 ,

AX-ll 3.17-4

4.19 FIRE PROTECTION AND DETECTION SYSTDi Applicability Applies to the fire protection and detection systems which protect systems and equipment required for safe shutdown.

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

Specifications 4.19.1 The 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 3 Years (c) High pressure service water pump capacity test Annually System Flow Test Every 3 Years (d)

(e) Alignment of fire protection valves Weekly (f) Sprinkler systems in safety related areas.

1. System functional test Annually

2. Inspection of spray headers Annually

3. Inspection of spray nozzle Annually (g) Fire hose stations

1. Visual inspection Monthly

2. Maintenance inspection Annually

3. Partial opening of fire hose station valve Every 3 Years 4.19.2 The fire detection system shall be tested for operability as follcws:

Item Frequency (a) Operability of detectors Semi-Annually

! (b) Operability of annunciators Every 2 Months 4.19.3 Penetration fire barriers protecting safety-related areas shall be verified functional by visual inspection at least once per 18 months.

l 4.19-1

~

s

~

'6. 0 ADMINISTRATIVE CONT 0LS 6.1 ORGANIZATION, REVIE*a', AND AUDIT 6.1.1 Organization 6.1.1.1 The station Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

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 te the Vice President, Steam Production, through the Manager, 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 specified 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 and experience described in Section 4 of the ANSI N18.1-1971,

" Selection and Training of Nuclear Power Plant Personnel."

.6.1.1.5 Retraining and replacement of station personnel shall be in accordance with Sec tion,5.5 of the ANS1 N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."

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

6.1.2 Technical Review and Control l i) m 0

l j

6.1.2.1 Activities dE

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

organi:ation. Each such procedure, or procedure change, shall be reviewed by an individual / group other than the individual / group which 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 temporary use by two members of the station staff, at least one of whom holds a Senior Reactor Operator's License on the unit (s) affected. Procedures and prm edure changes shall be approved prior to use or within seven days of receiving temporary approv-al for use by the station Manager; or by the Operating Superintendent, the Technical Servlees Superintendent or the Maintenance Superintendent, a3 previously designated by the station Manager.

b. Proposed changes to the Technical Specifications shall bc ;)repared by a qualified individual / organization. The preparation of each proposed Tech-nical Specifications change shall be reviewed by an individual / group other than the individual / group wnich prepared the proposed change, but who may

3 be from the same organization as the individual / group which prepared the proposed change. Proposed changes to the Technical Specifications shall be approved by the station Manager.

c. Proponed mod!Cicalions to station nucient safety-reinted structuren.

aystems and component s shall he desir.ned by a qu21 tfled Individual /

organir.ntion. F.ach such modification shall be '.eviewed by an individual /

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

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

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 such reviews. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated station review personnel,

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

g. The station !!anager shall assure the performsnee of special reviews and investigations, and the preparation and subuittal of reports thereon, as requested by the Vice Presioent, Steam 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 Director of the Nuclear Safety keview Board.

i. The station emergency plan, and inplementing 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; and to the Director of the Nucl,.: Safety Review Beard.

j. The station manager shall as o e that an independent fire pro-tection and loss prevention 1spection and audit shall be per-fermed annually utilizing quol.fied off-site personnel and that an inspection and audit by a qualified fire censultant shall be performad at intervals ne greater than three years.

~ __. .

3

g. Any oth:r ersa of ctction oprration considsrtd appropriata by ths NSRB

~ ' ' or the Vice President, Steak Production.

h. The station fire protection program and implementing procedures at least once per 24smonths.

6.1.3.5 Responsibilities and Authorities

a. The NSRB shall report to and advise the Vice President, Steam Production on those areas of responsibility specified in Specifications 6.1.3.3 and 6.1.3.4.

b. Minutes shall be prepared and forwarded to the Vice President, Steam Production, and to the Senior Vice President, Production and Transmission, within 14 days following each formal meeting of the NSRB.

c. Records of activities performed in accordance with Specifications 6.1.3.3 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 Transmission and to the management positions responsible for the areas audited within 30 days of completion of each audit.

6.1-5

S e

TABLE 6.1-1 '

Minimima Operating Shift Requirements Uith Fuel in the Three Reactor Vessels Unit 1 or 2 Above Units 1 and 2 Above Unita 1 or 2 Above Unita 1 and 2 Cold Unita 1, 2 Units 1, 2 Mistanas AEC Cold $butdown; Unit Cold Shutdown; Unit Cold Simstdoung Unit sisatJoung Unit 3 - and 3 Above and 3 Cold License Requirements 1 Cold shutdoum 3 Cold Shut 4oum 3 Abows Cold Shasedaue Above Cold Shutdoun Cold Shtdous Shutdeum Seafor Reactor Operator 2 2 2 2 3 2

)

Reactor Operator 4 4 4 4 4 3 Unlicensed Operator 2 2 2 2 4 Additional Requirements:

1. One licenaud operator per unit shall be in the Control Room at all time when there is fuel in the reactor vessel.

2. Two licensed operators shall be in the Control Room during startup and scheduled staatdown of a reactor.

o-

3. At least one licensed operator shall be in the reactor building when fuel handling operations

[ in the reactor building are in progrees.

g

4. An operator holding a Senior Reactor Operator license and assigned no other operational duties shall be in direct charge of refueling operations.

Q

5. At least one person per shif t shall have sufficient training to perform routine health physics requirements.

6. If the computer for a reactor is inoperable for more than*eight hours, an operator in addition to those required above shall supplemment the shif t crew. ======

7. A fire brigade of 3 members shall be maintained on site at all times. This excludes 3 members an====

, of the minimum operating shift requirements that are required to be present in the control rooms.  %

3:=

r--

,