ML20206H557

Proposed Tech Specs Change 138 Re Removal of Fire Protection Requirements from Tech Specs & Placement in Plant Procedures

ML20206H557
Person / Time
Site:	Beaver Valley
Issue date:	04/07/1987
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20206H260	List: ML20206H257 ML20206H557 ML20206H628
References
NUDOCS 8704150388
Download: ML20206H557 (89)

Text

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- ATTACHMENT A Revise the technical specifications as follows:

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B 3/4 3-3 B 3/4 3-3 B 3/4 7-7 B 3/4 7-7 6-1 6-1 6-5 6-5 6-23 6-23 License Condition 2.c(5) Revised License condition 2.c(5) 8704150388 8704o7 PDR ADOCK 05000334 P pyg ,

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TABLE 4.3-6.

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REMOTE SHUTDOWN MONITORING INSTRUMENTATION- '

g SURVEILLANCE REQUIREMENTS c

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' CHANNEL CHANNEL.

INSTRUMENT CHECK CALIBRATION E

M e l'. Intermediate Range Nuclear Flux M N.A.

'2. Intermediate Range Startup Rate M- N.A.

3.. Source Range Nuclear Flux (1) M(4)- N.A.

4. Source Range Startup Rate (1) M(4) N.A.

l S. Reactor Coolant Temperature - Hot Leg M R

{ 6. Reactor Coolant Temperature - Cold Leg M R

7. Pres'urizer s Pressure M R-y 8. Pressurizer Level M 'R

9. Steam Generator Pressure- M R 1 10. Steam Generator. Level M R

$ 11. RHR Temperature - HX Outlet (3)- M(5) R w

D 12. Auxiliary Feedwater Flow Rate' S/U(2) R' w

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, 3 Notation (1) Operability required'in accordance with Specification 3.3.1.1.

(2) . Channel check to be performed _in conjunction with Surveillance Requirement 4.7.1.2.a.9'following'an extended plant _ outage.

(3) Operability required in accordance with. Specification 3.4.1.3.

-(4) Below P-6.

(5) Channel check to be performed in conjunction with-Surveillance Requirement 4.4.1.3.1~.

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INSTRUMENTATION.

i BASES

,, 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that= sufficient capability is available to permit shutdown. and

. maintenance of HOT STANDBY of the facility.from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine . detection system. ensures that

sufficient capability is available to promptly detect and initiate protective action in the event' of an accidental chlorine release.

This capability is required to protect control room personnel and'is consistent with the recommendations of Regulatory. Guide 1.95,.

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" Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975. -

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3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION I The . OPERABILITY of the accident monitoring instrumentation '

ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with.the recommendations

{ of Regulatory Guide 1.97, " Instrumentation 'for' Light-Water-Cooled'

Nuclear Plants to Assess Plant Conditions During and Following an ,

i Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned" Task t j Force Status Report and Short-Term Recommendations." i 4

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BEAVER VALLEY - UNIT 1 B 3/4 3-3

. PROPOSED WORDING

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• PLANT SYSTEMS BASES 3/4.7.13 AUXILIARY RIVER WATER SYSTEM The operability of the ARWS ensures that sufficient cooling capacity is available to bring the reactor to a cold shutdown condition in the event that a barge explosion at the station's intake structure or any other extremely remote event would render all of the normal RIVER WATER SYSTEM supply pumps inoperable.

BE.'VER VALLEY - UNIT 1 B 3/4 7-7 PROPOSED WORDING

.[ 6.0' ADMINISTRATIVE ~ CONTROLS

( 6.1- RESPONSIBILITY 4

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 i 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

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The Facility organization shall be as sh'own on Figure 6.2-2 and:

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

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c. At least two licensed Operators shall be in the control room

, during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.-

1 d. An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.

a e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a -licensed Senior' Reactor Operator or Senior Reactor Operator. Limited to Fuel Handling

- who has other concurrent responsibilities during this

operation. l

f. Administrative procedures shall be developed and implemented

to limit the working hours of unit staff who perform safety-related functions; senior reactor operators, reactor

operators, radiation control- technicians, auxiliary operators, meter and control repairman, and all personnel-actually performing work on safety related equipment.

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i- BEAVER VALLEY - UNIT 1 6 i PROPOSED WORDING t

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• ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiological Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

I 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)

FUNCTION 6.5.1.1 The OSC shall function to advise the Plant Manager on all matters related to nuclear safety and shall provide review capability in the areas of:

a. nuclear power plant operations

b. radiological safety

c. maintenance

d. nuclear engineering

e. nuclear power plant testing

f. technical advisory engineering

g. chemistry

h. quality control

1. instrumentation and control 6.5.1.2 The Plant Safety Review Director is the OSC Chairman and shall appoint all members of the OSC. The membership shall consist of a minimum of one individual from each of the areas designated in 6.5.1.1.

OSC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.

BEAVER VALLEY - UNIT 1 6-5 PROPOSED WORDING l

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• ADMINISTRATIVE CONTROLS

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b. Inoperable Seismic Monitoring Instrumentation Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2'

e. Sealed source leakage in excuss of limits, Specification 4.7.9.1.3.

f. Miscellaneous reporting requirements specified in the Action l Statements for Radiological Effluent Technical Specifications,

g. Containment Inspection Report, Specification 4.6.1.6.2. l 6.1 RECORD RETENTION 6.10.1 The following records shall be retained for at least five (5) years:

a. Records and logs of facility operation covering time interval at each power level,

b. Records and logs of principal maintenance activities, inspections, repair and replac2 ment of principal items of equipment related to nuclear safe:y.

c. All REPORTABLE EVENTS D. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of reactor tests and experiments,

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

1. Records of annual physical inventory of all sealed source material of record.

BEAVER VALLEY - UNIT 1 6-23 PROPOSED WORDING l

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Revised License Condition 2.c(5)

. . . (5)~ Fire Protection The Licensee shall implement and maintain all. provisions of the approved fire protection- program as described in.the UFSAR. for- the facility and subject. to the -following provision: The Licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

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, . ATTACHMENT B

[ Proposed Technical Specification-Change No. 138

!, No Significant Hazard Consideration 3

This amendment request consists of deleting sections 3.3.3.6, 3.7.14.1, 3.~7.14.2, 3.7.14.3, 3.7.14.4, 3.7.14.5, 3.7.15, 6.2.2.f and 6.4.2. revise section 6.9.2, and license condition 2.C(5). The following discussions address these changes and their corresponding no significant hazard evaluations.

4 1. Section 3.3.3.6 (Fire Detection Instrumentation) has been-deleted, and the requirements contained-therein-have been- ,

i transferred to the UFSAR and plant operational procedures. ,

A note (next page is 3/4 3-49) has been-added.to page  !

, 3/4 3-46 to reflect the above change. Section 6.9.2 item f I I

has been. deleted to reflect-the above change. Table 3.3-10, Fire Detection. Instruments, has been transferred to i administrative procedures. Item 18 of- Technical Specification Table 3.3-10 will be replaced by the Primary..

Auxiliary Building -(PAB) smoke detection instruments which i are included in administrative procedures. Item .18 of Technical' Specification Table 3.3-10,. which_ provides the r l fire detection instruments for the Unit 2 control room zones 7, 8 and 9, . will. be included in the administrative procedures. The Chemical Addition Building smoke detectors l will be included as Item 26 in administrative procedures.

j These instruments have been added to ' administrative procedures to ensure fire detection capability for safety related equipment located in the PAB and Chemical Addition i 1

Building.  !

I j a) This change does not involve a significant increase in

! the probability or consequences of an accident i previously evaluated. No changes to the requirements  ;

l' have been made. This change simply removes the fire f detection instrumentation requirements from the ;

1 Technical Specifications and places them into the site

! fire protection program and procedures'and the UFSAR r i without altering them. Review of the Fire Protection program and its revisions will be1the responsibility of the Onsite Safety Committee (OSC) just as it has always i been the responsibility of the OSC to review changes to .

fire protection requirements when they were part of the t Technical Specifications.

b) This change does not create the possibility of'a new or j different kind of accident from any previously

evaluated. The proposed change does not alter the 4

requirements; it just moves ,them from the Technical i Specifications to the UFSAR. Plant. procedures will l continue - to provide the specific instructions for i implementing the LCO, action, and surveillance i requirements. There has been no reduction in j commitments and, as incorporated- into the plant

procedures, this change meets the requirements of the j existing Technical Specifications.

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.Attcchment B (Continu:d)

, Propored Technical Specification ~Chengo No. 138 ,

. Pags 2 )

l c) This change does not involve a significant reduction in l the margin of safety. No change is being proposed to l the requirements themselves. Section 3.3.3.6_is being deleted, and the requirements contained therein are being incorporated into the UFSAR. Plant procedures will continue to' provide - the specific instructions necessary for the implementation of the requirements, just as they had when the requirements resided in the Technical Specifications. Fire Protection Program commitments and amendments will by this process be transferred from the jurisdiction of 10 CFR 50.90 to 10 CFR 50.71(e). The reportability criteria of 10 CFR 50.72 and 10 CFR 50.73 are still applicable.

2. Section 3.7.14.1 (Fire Suppression Water System) is deleted. All of the requirements contained therein, with the exception of the special reporting requirements have been transferred to the UFSAR and plant operational procedures. Section 6.9.2 item g has been deleted to reflect the above change.

a) This change does not involve a significant increase in the probability or consequences of an accident pre-viously evaluated. The accident analysis does not

assume that a design basis accident occurs simul-

taneously with a fire, and the fire hazards analysis does not rely solely on automatic. fire suppression systems. . In addition, backup manual fire suppression capabilities are available. Other than the deletion of the special reporting requirements, no changes to the requirements have been made. This change for the most part simply removes the fire suppression water system requirements from the Technical Specifications and places them into the plant procedures and the UFSAR without altering them. Review of the Fire Protection Program and its revisions will be the responsibility of the OSC, just as it has always been the responsibility of he OSC to review changes to fire protection requirements when they were part- of the Technical Specifications.  ;

b) This change does not create the possibility of a new or different kind of accident frota any previously evaluated since the accident analysis does not assume that a design basis accident occurs simultaneously with 4

a fire and the fire hazards analysis does not rely solely on automatic fire suppression systems.

! Plant procedures will require establishment of a backup fire suppression system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In order to l ensure that actions 'are taken if the backup -fire suppression water system is not available, plant procedures will require actions designed to minimize the risk of fire. Provisions for the review of future changes to the requirements are dictated by the existing section 6.8.1.

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.Attcchm:nt B (Continu:d)

. Propoced Technical Sp cification Changa No. 138 Pags 3 c) This change does not involve a significant reduction in the margin of safety since fires are not assumed to occur simultaneously with a design basis accident. In addition, several means of fire detection and fire protection are still operable, since they are not affected by the loss of the water suppression system.

Fire detection instrumentation is available allowing detection of a fire and response by plant personnel using operable fire fighting capabilities. Plant fire barriers providing fire isolation of safety-related equipment from non-safety-related equipment and between trains of safety-related equipment are still operable.

Plant procedures will continue to provide the specific instructions necessary for the implementation of the requirements from specification 3.7.14.1. Fire Pro-tection Program commitments and amendments will by this process be transferred from the jurisdiction of 10 CFR 50.90 to 10 CFR 50.71(e). The reportability criteria of 10 CFR 50.72 and 10 CFR 50.73 are still applicable.

In summary, loss of the normal fire suppression water system does not affect the probability of having an accident. If the backup suppression system is not-available, additional compensatory actions will be j taken as discussed above, and therefore, shutdown of the unit is not warranted. Additionally, unit power level or changes in operating mode will not affect the remaining suppression or backup suppression capability to handle a fire, therefore, the application of

Technical Specification 3.0.4 is not warranted.

3. Section 3.7.14.2 (Spray and/or Sprinkler Systems), 3.7.14.3 (CO2 Systems), 3.7.14.4 (Fire Hose Stations), 3.7.14.5 (Halon Systems), and 3.7.15 (Fire Barrier Penetrations) are deleted, and the requirements contained therein have been transferred to the plant operational procedures. Section 6.9.2 item g has been deleted to reflect the above changes.

a) This change does not involve a significant increase in the probability or consequences of an accident

, previously evaluated. No changes to the requirements have been made. This change simply removes the spray and/or sprinkler system, halon systems, CO2 system, fire hose station, and fire barrier penetration requirements from the Technical Specifications and.

places them into plant procedures and the-UFSAR without altering them. Review of the Fire Protection program and its revisions will be the responsibility of the Onsite Safety Committee (OSC) just as it has always been the responsibility of.the OSC to review changes to fire protection requirements when they were part of the Technical Specifications.

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i Attcchment'B'(Continutd). ..

. - Proposed Tachnical Spacification Changa'No._138 l

-*. Page 4 ]

I b) This change lioes not create the possibility.of a.new or

'different kind of . accident 1 ~from; anyf previously.

evaluated., The _ proposed change does.:not alter the l requirements; it. just moves them from the1 Technical 1 Specifications to..the UFSAR. Plant-procedures;will i continue to provide the ' specific instructions .for

, implementing the LCO, action,. and . surveillance requirements. .

There has been. no-_ reduction: in -

i- commitments- and, as incorporated. into the - plant:

procedures, -this change meets.the requirements of the existing Technical Specifications.

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c) This change does not' involve a significant reduction?in the. margin of. safety. 'No. change is-being. proposed for the requirements. themselves.~ Sections. 3.7.14.2, 3.7.14.3, 3.7.14.4, 3.7.14.5 and. 3.7.15. are- being i deleted,. _and~ the requirements ~ contained :therein are being incorporated into the .UFSAR. Plant procedures will continue to -provide _the specific instructions i necessary for the implementation of the requirements, i just as they had when the requirementsLresided in-the Technical Specifications.  : Fire . Protection Program

! commitments and amendments .will by this process be a

transferred from the jurisdiction of 10~CFR 50.90 to 10 i CFR 50.71(e). The reportability- criteria of 10 CFR 1

50.72 and 10 CFR 50.73 are.still applicable.

4. Section 6.2.2.f Site Fire Brigade Requirementsrand Section

{ 6.4.2 have been deleted, and the requirements contained

therein have been transferred. to the . plant:-operational' procedures.

change does not involve a significant incre5se in

a) This i the probability or consequences of- an a'ecident

previously evaluated. No changes to the. requirements have been made. This change simply removes the-site

! fire brigade requirements from -the Technical

! Specifications and places them into plant' procedures i and- the UFSAR without altering .them. Review of.the i Fire Protection program and its: revisions will be the 1

responsibility of the :Onsite' Safety- Committee.(OSC) just as it has always been the responsibility of the

, OSC- to review changes to fire protection requirements when they.were part of the. Technical Specifications.-

b) This change does.not create the possibility of a new or-l different kind of- accident from any previously i evaluated. The proposed -change does- not alter'the requirements; it just moves them- from the Technical Specifications taa the UFSAR. Plant procedures will continue- to provide the specific instructions for implementing the LCO, action, and- surveillance j requirements. There has been no reduction in commitments and, as -incorporated into. the' plant procedures, this change meets the requirementslof the.

existing Technical Specifications.

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• Attechment-B (Continued)

• Propoced-Technical Specification'Changa No. 138 t-Pago 5 -

I c) This . change does not involve a significant reduction in the margin. of safety. No change is being proposed for

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the requirements themselves. Section. 6.2.2.f .andL Section 6.4.2 are being deleted,.and the requirements contained therein. are being--incorporated into .the UFSAR. Plant procedures.will continue to provide the

specific instructions necessary for the implementation of the. requirements,- just as they had when the.

requirements resided in the Technical Specifications.

Fire Protection Program commitments and amendments will.

by-. this-process be transferred from the jurisdiction of 10 CFR -50.90 to 10 'CFR 50.71(e).. The reportability criteria of 10 CFR 150.72 and 10 CFR 50.73.are still applicable.

5. License condition 2.C.(5) has been replaced by the standard condition provided in section F of Generic Letter 86-10, Implementation. of Fire Protection Requirements. The previous license condition 2.c(5) referred to modifications identified in _ Table 1- of the Fire Protection Safety; Evaluation Report for BVPS, Unit. 1, dated May 9, 1979.

! These modifications have all been completed, therefore, this

• i condition is no longer necessary.

a) This change does not involve a significant increase in

. the probability or consequences of an accident previously evaluated. The change'in license-conditions

from those previously incorporated into the license to the one presented in Generic Letter 86-10_does not l result in any loss of control of the change process.

Previously, changes to the Fire Protection Program that

decreased the level of fire' protection in the plant could only be made with' prior Commission approval utilizing the license amendment -process (10 CFR 50.90). Since the Fire Protection program and the former Technical Specifications .are now incorporated into the UFSAR, their changes fall under 10 CFR 50.59 which contains the same record keeping requirement.

b) This change does not create the possibility of a new or

different kind of accident from any previously evaluated.- The proposed license conditions do not involve any significant change in requirements and are recommended by the NRC in Generic Letter 86-10.

c) This change does not involve /a significant reduction in i- the margin of safety. The proposed license condition does not involve any significant change in requirements and was recommended.by the NRC in Generic Letter 86-10.

i Fire Protection program commitments and amendments will by this process be transferred from the jurisdiction of 10 CFR 50.90 to 10 CFR 50.71(e). .The reportability-l criteria of 10 CFR 50.72 and 10 CFR150.73 are:still.

applicable.-

Attichment B (Continued) .

• Propor:d TachnicnL Specification Changa No. 138  :

Pags 6 .

3 Conclusion The proposed changes do not' involve any physical change to-plant safety related systems, components or structures, will not' increase the likelihood of a malfunction of safety related equipment, increase i the consequences of an accident previously analyzed, nor create'the-1 . possibility of a malfunction 'different than previously evaluated.

The function and operation of the Fire Protection Systems remains unchanged. Therefore/c based on the above, the changes have been determined- to be ad.ministrative in nature and it is proposed to

-characterize the -change as involving no significant hazards "considerction .

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ATTACHMENT' C Proposed Changes to'BVPS Unit 1 Updated Final Safety Analysis Report 1

Section 9.10 " Fire Protection'.'

(Changes noted by revision bar at margin) s s

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H BVPS-1-UPDATED FSAR Rev. 5 (1/87) i

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i 9.10 FIRE-PROTECTION SYSTEM l Based- on guidance provided' in Generic Letter 86-10(d, the

Facility Operating License was amended such.that the fire protection

requirements previously included'in the Technical Specifications were relocated to this section of' the UFSAR and Site Administrative Procedure (SAP) 9D Fire Protection, including the following license ,

condition:

! The _ licensee shall implement _ and. maintain- all provisions of-the approved fire protection program as described in the UFSAR for the facility and subject to the following provision;'the licensee may make j, changes _ to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the

ability to achieve and maintain safe shutdown in the event of a fire.

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9.10.1 Design Bases G

The fire protection system for Beaver Valley Power Station - Unit l' (BVPS-1) has been designed such that any single fire will not cause an unacceptable risk to public health and safety, will not prevent.the performance of necessary safe shutdown functions, and will not significantly increase the risk of radioactive release to the environment.

A fire occurring at both Units simultaneously is beyond the design basis for the site.(d The likelihood of a fire spreading from one Unit to the other is considered unlikely due to the following:

j plant design features and existing fire barriers relative to fire loadings in each fire area, 1

physical separation between BVPS-1 and BVPS-2 plant structures with the exception of shared facilities.(i.e~., intake structure and control room) as defined in Section 1.7 which have been

analyzed per GDC 5, and I

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defense-in-depth criterion utilized at both BVPS-1 and BVPS-2 relative to fire prevention, detection, and suppression i capabilities.

The station is designed on the basis _of minimizing the .use of.

combustible materials and of the use of fire-resistant materials to the greatest extent possible.

A -Fire Brigade of at least 5 members shall be maintained on site at all times. The Fire . Brigade shall not ' include 3 members ofithe

minimum shift crew necessary for safe shutdown of the unit or any

personnel required for other escential functions during a fire emergency.

I I 9.10-1

BVPS-1-UPDATED'FSAR Rov. 5 (1/87) ,

l The system is designed in accordance with the standards of the National Fire Protection Association and is generally based on the recommendations of the- insurance underwriter. (American Nuclear fire protection system is designed on the basis that ~

Insurers). The rupture or inadvertent operation will not significantly impair the l safety capability of structures, systems, or components important to i safety or designed to seismic Class I requirements.

Fire ProtectionU), requires that each 10 CFR 50 Part 50.48 -

i operating nuclear power plant have a fire protection plan that i

. satisfies- GDC 3 of Appendix A. The plan, described in SAP 9D Fire Protection, identifies the overall fire protection program, the a

organization and responsibilities for the program, and outlines the ,  !

plan for fire protection for the site. The plan also describes j specific features necessary to implement the program and the means to limit fire damage to structures, systems and components important to e safety so that the capability to safely shutdown the plant is ensured.

Certain fire protection features that have been accepted by the NRC to ,

satisfy the pYovisions of Appendix A to Branch Technical Position BTP APCSB 9.5-1 Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976 are reflected in the Fire Protection Safety Evaluation Report which was issued by the NRC for BVPS-1 and documented as Amendment No. 18 to the Technical Specifications, dated l

June 6, 1979.O O j

! Clarification and guidance with respect to permissible alternatives to satisfy Appendix A to BTP APCSB 9.5-1 is provided in the NRC document i Nuclear Plant Fire Protection Functional Responsibilities, Administrative Control and Quality AssuranceU>. BVPS-1 complies with this document which meets the fire protection QA program criteria of Appendix A to BTP 9.5-1.

The Operations QA Program for Fire Protection'for BVPS-1 is identified in the DLC Quality Assurance Program Appendix C - Fire Protection.

l Appendix R to 10 CFR Part 50(5) establishes fire protection features required to satisfy GDC 3 with respect to certain generic issues for BVPS-1 (licensed to operate prior to January 1, 1979),

applicable only as per the following:

-Section III.G: Safe Shutdown Capability

-Section III.J: Emergency Lighting

-Section III.O: RCP Oil Collection System 1

The NRC Safety Evaluation Report for Appendix R-to 10 CFR.50 was issued on January. 5,~1983, for BVPS-1. Exemptions for specific fire areas of the plant were granted per NRC letters dated March 14, 1983, August 30, 1984 and December 4, 1986. 'S

, 9.10.2 Description The fire protection systems are shown schematically in Figures 9.10-1 and 9.10-2. Design data for major components of the fire protection i system are given in Table 9.10-1.

i 9.10-2 I l

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BVPS-1-UPDATED FSAR Rev. 5 (1/87)

G Intake Structure The intake structure compartments which house the river water, raw water and fire pumps are separated from each adjacent compartment by concrete walls. There are two doors in each compartment. Each of the

total of six openings are provided with both fire doors and watertight

, flood doors. All fire doors between compartments are maintained in a closed The A, B and C cubicles are equipped with several i

ionization. position.

smoke . detectors which annunciate in the main control room.

The D cubicle, which houses the diesel fire pump, is equipped with i ' heat detectors which also annunciate in the control room.

, The amount of combustible material located within these compartments i has been minimized. The entry doors into the four pump cubicles are security card-key ~ access vital area doors and, as such, are eletrically supervised to ensure proper closure. The doors between

! pump cubicles are administrative 1y controlled to ensure proper closure i of the ' doors. The normally closed interconnecting fire door will i prevent the spread of fire to the adjacent pump cubicle. This isolation will limit the fire damage to one compartment.

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{. 9.10.3 Evaluation 1

An Appendix R report has been prepared to outline the BVPS, Unit No. 1 L position on 10 CFR 50 Appendix R Sections III-G Fire Protection of l, Safe Shutdown Capability, III-J Emergency Lighting, Collection System for Reactor Coolant PumpU). andIII-OOill This report contains the fire hazards analysis and summarizes'the investigative electrical analysis performed for BVPS -Unit No. 1 to determine if fires within a single area could jeopardize the ability to safely shut down the plant. The report will be administratively controlled, and updated periodically.

The fire protection system provides a reliable source of water or other fire fighting agents to all portions of the station.

Cold weather operation is assured in that yard piping is buried below

{ the frost line and outdoor piping serving transformers is of the dry i pipe design. All other portions of the fire protection systems are

' located in heated areas and are not subject to freezing conditions.

Dual 100 percent design capacity fire pumps are provided and arranged to start in sequence, ensuring adequate pressure in the fire mains.

1 The fire pump house electric heating system and motor-driven fire pump power supply originates from two separate sources with power cable run through buried conduit. The fuel oil supply and starting equipment

. for the diesel engine driven fire pump is of the type approved by

! Underwriters Laboratories for fire pump service.

Fire detection and system operation are automatically indicated in the

, control room by audible alarms and visual annunciation. Trouble lamps l are provided to monitor the operability of the fire detection system.

9.10-9

. BVPS-1-UPDATED FSAR Rev. 5 (1/87) .

\

. l These lamps alse provide indication of electrical faults in the fire i detection system. I l

The fire detection system is supplied by two 120v a-c sources, one )

normal _and one emergency. Failure of a single detector will not i render the system inoperable.

The engineered safety features equipment served by water spray fire l protection are the charcoal cells in the main exhaust filter bank l housings, component cooling water pumps and auxiliary feedwater pumps, l and the residual heat removal pumps. ,

The only engineered safety feature equipment served by the CO2 fire protection system susceptible to adverse effects are the emergency - I diesel generators. CO2 is prevented from discharging into the diesel generator cubicles following a CIB signal and undervoltage .'

condition on the emergency busses. Release of CO 2'during operation l of the diesel generator could result in stalling the diesel generator l engine by the displacement of combustion air with CO 2. When CO2 j is discharged in an emergency diesel generator cubicle, safe plant l shutdown is assured under the single ' failure criteria by the  !

separation of both diesel generators by a fire wall.

Other electrical areas protected by CO2, but'which are not adversely affected by the release of CO2 , are the cable vaults and cable tray mezzanine.

Design features incorporated in the plant include the use of '

noncombustible materials as much as possible to minimize the potential for fire occurrences. Fire rated walls and doors and other fire barriers are also provided to prevent the spread of fire.

Fire protection equipment is of a type identified in the list of approved equipment issued by the Underwriter's Laboratories and conforms to the requirements of the insurance carrier (ANI) and the Standards for Sprinkler Systems NFPA No. 13,' CO2 NFPA No. 12 and Water Spray Systems NFPA No. 15. Compliance with the requirements of the above insurance interests and standards ensures the reliability of the fire protection equipment based on years of previous use and proven performance. -

9.10.4 Tests and Inspections Testing and inspection of the fire protection system is conducted in accordance with Site Administrative Procedure 9D. .

,_ Water Systems ~

Testing of the water system includes:

1

1. The diesel engine and electric motor driven fire pumps are subjected to a regular weekly operational test. The electric motor and diesel engine driven fire pumps are flow tested yearly to ensure proper functioning when required.

l 9.10-10

BVPS-1-UPDATED FSAR Rav. 5 (1/87)

3. Inspection and verification that system mode selector switches are.

correctly positioned.

4. Check of the electrolyte level in the batteries.

9.10.5 Fire Protection Bases i

9.10.5.1 Fire Detection Instrumentation Operability of the fire detection instrumentation ensures that

! adequate warning capability is available for the prompt detection of i fires. This capability is required in order to detect and locate  !

fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and- is an l 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 - or- -in containment air temperature monitoring in the affected areas is required to provide detection capability until the'~ inoperable instrumentation is restored to operability. I 9.10.5.2 Fire Suppression Systems The operability of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish i fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the i water system, spray and/or sprinklers, CO2, Halon 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 facility fire protection program.

i

! In the event that portions of the fire suppression systems are

! inoperable, alternate backup firefighting equipment is required to be made available in the affected areas until'the inoperable equipment is restored to service. When the inoperable firefighting equipment is intended for .use as a backup means of fire suppression, a longer ,

period of time is allowed to provide an alternate:means of fire '

i fighting than if the inoperable equipment is the primary means of-fire-suppression. -_

. - . . .. . .. ~

4 The test requirements identified in Site Administrative Procedure 9D l 1 provide assurance that the minimum operability. requirements of the l fire suppression systems are met. An allowance is made for ensuring a sufficient volume of Halon in the Halon storage tanks by verifying either the weight or the level of the tanks. The halon systemscare _

indoor, underfloor cable area systems not susceptible to outdoor weather conditions. The systems are dry pipe (rust is not expected)

gas suppression systems.

In the event the fire suppression water mystem becomes inoperacle,

! corrective measures must be taken as defined in the administrative procedures since this system provides the major fire suppression i capability of the plant. l i 1 l

l 9.10-12

BVPS-1-UPDATED FSAR Rnv. 5 (1/87) 9.10.5.3 Fire Rated Assemblies The'. operability of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment. The fire barriers, fire barrier penetrations for conduits, cable trays and piping, fire windows, fire dampers, and fire doors are periodically inspected to verify their operability.

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BVPS-1-UPDATED FSAR Rav. 5 (1/87) 1

, References for Section 9.10

1. Appendix A to Branch Technical Position APCSB 9.5-1, Guidelines for Fire Protection for Nuclear . Power Plants Docketed Prior to July 1, 1976.

2. Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance, NRC letter. dated August 29, 1977.

t

3. 10 CFR 50.48 - Fire Protection for Operating-Nuclear Power Plants.

4. Amendment No. 18 to the Beaver Valley Power Station ~ Unit No.-1, j Operating License DPR-66.

i~

5. Appendix R to 10 CFR 50.

6. NRC Generic Letter 86-10.

i 7. Updated Fire Protection Appendix R Review Report for BVPS Unit 1.

8. Letter from S. A. Varga, . Chief Operating Reactors Branch #1, Division of Licensing, NRC to J. J. Carey Vice' President, Nuclear Group, DLC, dated May 14, 1985.

Subject:

" Clarification of'~

Amendment 18, Fire Hydrant Barrel Inspection' Frequency".

i

9. NUREG-1057 Safety Evaluation Report Related to the Operation of Beaver Valley Power Station, Unit 2.

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I l 9.10-14 l

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l

A T T A C H ?! E N T D Station Administrative Procedure 9-D

" Fire Protection Program" l

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DUQUESNE LIGHT COMPANY-

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+' Nuclear Group Site' Administrative Procedures LIST OF EFFECTIVE PAGES Chapter 9D Title FIRE-PROTECTION Page Nos. Revision No. Effective Date i-iv - 4 1-64 4 Page'11 of iv Revision 4-m._________________.____ t_E_________

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Site Administrative Procedures Chapter 9D-FIRE PROTECTION Chapter Index Page i

l I. PURPOSE' 1 t

II. APPLICABILITY 1-

.III. DEFINITIONS. 1-1 IV. ORGANIZATION AND RESPONSIBILITIES- 2 V. REFERENCES 7 VI. INSTRUCTIONS 8 i A. Requirements 8

B. Operation 9-C. Maintenance 10 1 D. Inspection and Testing 10 E. Control of Ignition Sources 10 F. Control of Combustibles and Flammable Liquids '11 G. Engineering Design and Procurement Document Control 11 H. Training 13 I. Prefire Plans 13 J. Quality Assurance 13 K. Physical Requirements 14

, L. Program Review 14

M. Records 14 N. Out-of-Service Requirements /Reportability 14 Figure 1 - Administrative Organizational Chart 15 '

Figure 2 - Site Fire Brigade Organizational Chart 16-Table 1 - Operability Requirements for Fire Protection System 17 Table 1.1 - Fire Detection Instruments - Unit 1 22 1 Table 1.2 - Fire Detection Instruments - Unit 2 24 Table 2 - Fire Protection System Surveillance Requirements 30 Table 3 - Fire Insurance (ANI) Requirements for Fire Protection System 41 Table 4 - Fire Insurance (ANI) Surveillance Requirements for Fire Protection i System 51

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Site-Administrative Procedures -

-Chapter 9D

FIRE PROTECTION Chapter Index Page.

Attachment A - Instructions, Updated Fire Protection

-Appendix R Review Report - BVPS Unit:1, and Fire Protection Safe Shutdown-Report - BVPS Unit 2- 61 Table 1A --(Attachment A) Unit 1 Fire Protection App. R Review Report Section Review Responsibilities? 62-Table 2A - (Attachment A) Unit 2 Fire Protection Safe Shutdown Report Sections Review-Responsibilities 63 Figure 1A - (Attachment A) Proposed Change Form _ 64

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. DUQUESNE LIGHT COMPANY Nuclear Group r f r, Site Administrative Procedures fi If f kjfu.d;s l  :. . .4 u a s m;g t;; ; g j Chapter 9D FIRE PROTECTION I. PURPOSE To define the administrative authorities, respansibilities and requirements of the Site Fire Protection Program.

II. APPLICABILITY Applies to all Nuclear Group personnel. The basic fire protection admir.istrative organization chart is shown on Figure 1.

III. DEFINTTIONS NOTE: Certain words (such as OPERABLE, CHANNEL FUNCTIONAL TEST, COLD SHUTDOWN, etc.) within this procedure are applicable to the definitions identified in the Technical Specifications, Section 1.0.

A. A Fire Area is the portion of a building or plant that is separated from other areas by boundary fire barriers (walls, floors, and ceilings including seals, fire dampers and doors). ,

B. Fire Barriers are those components of construction (walls, floors, ceilings) that are rated in hours of fire resistance to prevent the spread of fire.

C. Sub-areas or Zones are subdivisions of fire areas in which fire suppression systems are designed to combat particular types of fires.

D. A Fire Watch or Fire Barrier Attendant is an individual assigned to attend an open fire barrier (fire door, penetration, etc.), or to monitor work procer.ses and l equipment or room conditions for possible fire hazards. The individual shall be trained in fire reporting procedures and portable fire extinguishing equipment.

l E. Ignition Source is any form of welding, soldering, brazing, I i

grinding or open flame work. j F. Combustible Material is any material that will burn or sustain the combustion process whether or not it exhibits flame under exposed fire conditions.

I G. Fire Retardant Wood is treated wood which exhibits fire l retardant properties or wood coated with a U.L. listed fire l

Page 1 of 64 Revision 4

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eg 72 e . t Nuc102r Group - Sita Administrctiva Proc:dur:s .

in : Chapttr 9D e 11 S I t ; (j a 1; u W 11 I ,v . ; .

• t>2ut t retardant compound having a flame spread rating of 25 or less.

H. Flammable Liquid is any liquid having a flash point below 100 F, except any mixture having components with flash points of 100*F or higher, the total of which make up 99% or more of the total volume of the mixture (i.e., solvents, etc.).

I. Combustible Liquid is any liquid having a flash point of 100 F or higher (i.e, lube oil, etc.).

J. Flash Point is the minimum temperature at which a liquid gives off vapor within a test vessel in sufficient concentration to form an ignitable mixture with air near the surface of the liquid.

K. Incipient-type Fire is a fire in its initial or beginning stage that can be controlled or extinguished by portable extinguishing equipment.

IV. ORGANIZATION AND RESPONSIBILITIES An Administrative Organization Chart, Figure 1 depicts the organization relative to the implementation of the fire protection program.

A. Supervisory personnel shall have the authority and responsibility for activities which are conducted by individuals under their general supervision with respect to the fire protection program.

B. Department Managers have responsibility for the activities conducted under their control. They,.in turn, are to hold accountable each supervisor, staff member and worker for the proper performance of activities associated with the fire protection program.

C. The Manager, Nuclear Engineering Department has responsibility for evaluating update requests and maintenance of the BVPS Unit 1 Updated Fire Protection Appendix R Review Report (UFPARRR) and the BVPS Unit 2 Fire Protection Safe Shutdown Report (FPSSR). He is responsible for assuring the periodic update of the Unit I and Unit 2 Reports and coordinating, tracking and processing of proposed changes as per the instructions provided in Attachment A of this procedure.

1 D. Section reviewers identified in Tables 1A and 2A of Attachment A are responsible for review of proposed changes ,

to the BVPS Unit 1 UFPARR and the BVPS Unit 2 FPSSR. i Personnel who prepare design changes, procedures, and NRC l correspondence that affect the Unit 1 or 2 Reports shall be l

)

I Page 2 of 64 Revision 4 j I I l

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e -1, e - t Nuclocr Group - Sito Administrrtivs Proc dur:2 ' -

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v Chtpt

s. : ve nio r is 9De U. ) 4 ; L. 5 responsible for initiating a change to the Reports utilizing the Proposed Change Form (Figure 1A).

E. The Manager, Nuclear Safety has responsibility for the overall administration of the fire protection program.

F. The Manager, Nuclear Training is responsible for development, implementation and revision of the fire training program, as well as coordinating, scheduling and providing classroom training.

G. The Director of Licensing is responsible for directing the efforts associated with the implementation of the fire protection program.

H. The Senior Licensing Supervisor has responsibility for supervising the Fire Protection Engineers, the overall implementation and assessment of effectiveness of the fire protection program, and for ensuring the development of proper fire protection training program for Nuclear Group personnel. He is also responsible for updating this procedure and performing the two-year review per SAP 11.

I. Fire Protection Engineers:

1. Responsible for monitoring the day-to-day implementation of the fire protection and prevention program.

2. Periodically assess the effectiveness of BVPS site fire protection program including Fire Brigade and fire protection training, fire drills and fire prevention program reviews, as required.

3. Assist in the design and selection of fire protection equipment.

4. Ensure the required fire protection and prevention procedures are in place and conduct a periodic review of such procedures.

5. Responsible for assisting other departments in development and implementation of procedures in matters affecting fire protection and prevention.

6. Responsible for evaluating and analyzing fire hazards and activities concerning fire protection and prevention.

7. Provide the Nuclear Group staff with technical information and expertise, as required, in the area of fire protection and prevention.

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["' P n ' M I; - ), 3 ,  ;- '! ~ ,1 I Nuclotr Group - Site Administrativa Procsduras l( ji IS }'(ht kU$f 9D dhrptar d i bfib t/IS E- 1

8. Responsible for processing of open burning permit for purposes of fire school tre'ning on an annual basis. from the State of Pennsylvania Bureau of Air-Quality Control.

J. Site Fire Brigade (Emergency Squad)

The structure of the Site Fire Brigade is shown in Figure 2 -

Site Fire Brigade (Emergency Squad) Organization Chart.

The function of the Fire Brigade (also referred to as the Emergency Squad) is to execute the necessary actions during an emergency to alleviate or minimize the consequences of the emergency.

.A Fire Brigade of at least 5 members shall be maintained on site at all times. The Fire Brigade shall^ not include 3 members of the minimum shift crew necessary for safe shutdown

, of the unit or any personnel required for other essential-

! functions during~a fire emergency.1 1

For fires in Zone I (basically Unit 1) and in areas common to both Units 1 and 2, the operating staf f at Unit I will assume primary Fire Brigade / Emergency Squad response with augmentation from Unit 2 personnel as necessary. For fires in Zone 2 (basically Unit 2), the operating staff at Unit 2 i

will assume primary Fire Brigade / Emergency Squad response with augmentation from Unit 1 personnel as necessary. This is assuming that both units are in normal (non-emergency) modes of operation.

Members of the Site Fire Brigade are assigned responsibility as follows:

l

1. Brigade Chief - Nuclear Station Operating Foreman (or, in his absence, as assigned by on-duty Shift Supervisor).

j a. Coordinates activities between Brigade & Control Room in the execution of emergency procedures.

i b. Determines what actions- are necessary to control and extinguish the fire as well as evaluating radiological hazards,

c. Insures that the necessary fire suppression systems are activated and that the Fire Brigade members safely utilize the proper equipment,

d. Augments the brigade with any available personnel

] or offsite organizations if the fire or first-aid emergency needs are such that the basic squad cannot adequately control the incident.

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u Nuc1ccr Group - Site Administrative Procsdursa

e. Determines -if an area should be evacuated of non-essential personnel and the escape route (s). that should be utilized.

2. Brigade Captain - huclear Control Operator (or, in his absence, as assigned by on-duty Shift Supervisor)

a. Assumes duties of the Chief in~his absence,

b. Directs the fire-fighting' . operations of the brigade,

c. Clears all energized equipment (without losing safe shutdown capability) which may endanger. safe-execution of fire fighting _ activities of the Brigade _ personnel. 3

d. Assures availability of necessary emergency equipment.

3. Additional Brigade members - a minimum of three persons total from any of the following job classifications:

- Nuclear Operators

- Nuclear Control Operators

- Shift Chemist (s)

- Shift Radiation Technician (s)

a. The additional Brigade members carry out the orders Captain of the Brigade in controlling and extinguishing the fire and/or caring' for the injured,

b. Each member of the Fire Brigade shall be capable of acting:

1) To alert the site Fire Brigade.

2) To recognize the fire alarm and respond properly and in accordance with approved pre-fire plan procedures / strategies.

3) To use available rescue and fire-fighting i equipment.  ;

4) To safely evacuate non-essential personnel from the affected area, if necessary.

5) To utilize the portable and fixed fire extinguishing suppression systems.

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-Nuclear Group - Site Administrative Procedures 1 UH daChapter Un!Miiuu 9D

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, 6) To cooperate with offsite fire department personnel in a coordinated fire-fighting effort.

.4. Fire Marshall (s) - A' fire marshall may be any one of the following:

- Any qualified brigade member. .

- Any DLC supervisor, qualified as-such through the fire training program >

a. Shall be qualified to handle incipient-type fires in accordance with fire training program.

b. Shall aid -in^ safely evacuating non-essential personnel from the area.

c. Shall assist the brigade so as to alleviate and minimize the consequences of the fire emergency.

5. Brigade Assistant (s); The Brigade Chief is authorized to commandeer any qualified DLC employee to assist- the Brigade force when such assistance is required. It is the responsibility of those commandeered DLC employees to perform the_ assigned tasks to the best of their ability without disruption to the Brigade force.

Page 6 of 64 Revision 4

(l ()OD j i } U U ..' .it j Chrpteh 9Di sis J Nuciser Group - Site Administrativa Proctduras V. REFERENCES *

1. BVPS Unit l'(2) FSAR, Section~ 9.10 (9.5.1 and Appendix 9.5A)

- Fire Protection System.

2. BVPS Unit 1 (2) Technical Specifications.

3. BVPS Unit 1 (2) Operating Manual, Chapter 33.(2.33), Fire

. Protection System.

4. BVPS Unit 1 (2) Operating Manual, Chapter 55A.4 (2.55A.4)

Operations Surveillance Tests, 1.33 (2.33) Series.

5. BVPS Unit 1 (2) Operating Manual, Chapter 56B (2.56B), Fire Prevention and Control.

6. BVPS Unit 1 (2) Operating Manual, Chapter ~56C (2.56C)

Alternate Safe Shutdown from Outside Control Room.

7. BVPS Unit 1 (2) Maintenance Manual, Chapter 1, Section Z, General Work Practice Procedures.

8. Fire Protection Safety Evaluation Report dated May 3, 1979 issued by the NRC for BVPS Unit 1.

9. Appendix A to Branch Technical Position APCSB 9.5-1,

Guidelines for Fire Protection for Nuclear Power Plants I Docketed Prior to July 1,1976.

4

10. Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance, NRC letter dated August 29, 1977.

4

11. 10 CFR 50.48 - Fire Protection for Operating Nuclear Power'-

Plant.

12. Appendix R to 10 CFR 50.

13. NRC Generic Letter 86-10.

14. Updated Fire Protection Appendix R Review Report for BVPS Unit 1.

15. Fire Protection Safe Shutdown Report for BVPS Unit 2.

16. NRC Inspection Report 89-17 for BVPS Unit 2.

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[ Nuciscr Group - Sita Administrstiva Procxdurcs [(f;[ [hj[Qhapteg 9D; . Lj sw L a VI. INSTRUCTIONS A. Requirements

1. All activities and requirements associated with the fire protection program shall be conducted in accordance with this procedure and the applicable fire protection sections of the FSAR for Units 1 and 2.

2. 10 CFR Part 50, General Design Criterion 3 (GDC 3) of Appendix A specifies that structures, systems, and components important to safety shall be designed and located to minimize the probability and effect of fires and explosions.

3. 10 CFR 50.48 -

" Fire Protection," requires each operating nuclear power plant have a fire protection plan that satisfies GDC 3 of Appendix A. The plan shall describe the overall fire protection program per the guidelines of Appendix A to BTP APCSB 9.5-1, " Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976."

a. A Fire Protection Safety Evaluation Report (dated May 3, 1979) was issued by the NRC for BVPS Unit 1 and documented as Amendment No. 18 to the Technical Specifications.

4. Clarification and guidance with respect to permissible alternatives to satisfy Appendix A to BTP APCSB 9.5-1 is provided in NRC document " Nuclear Plant Fire Protection Functional Responsibilities, Administrative Control and Quality Assurance." Compliance to this document is required to meet the fire protection QA program criteria of Appendix A to BTP 9.5-1 for BVPS Unit 1.

5. Appendix R to 10 CFR Part 50 establishes fire protection features required to satisfy GDC 3 for BVPS Unit 1 as follows:

- Section III.G; Safe Shutdown Capability

- Section III.J; Emergency Lighting

- Section III.0; RCP Oil Collection System An Appendix R report (" Updated Fire Protection Appendix R Review") was prepared for BVPS Unit 1 which contains the fire hazards analysis and summarizes the investigative electrical analysis performed for BVPS Unit 1 to determine if fires within a single area could jeopardize the ability to safely shutdown the plant.

NRC Safety Evaluation Report for Appendix R to 10 CFR 50 was issued on January 5, 1983, for BVPS Unit 1.

Page 8 of 64 Revision 4

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lNuc1 car Group'.- Site Administrative Procsdursa (~ .

Csphpq) '

b.

Exemptions

for specific fire : areas of the' plant were granted per NRC letters' dated March 14,'1983; August 30,-

L 1984; and December 4, 1986.

g Branch Technical Position (BTP) 'CMEB 9.5-1, which is

~

! 6.

part of. the acceptance criteria of Standard Review Plan 9.5.1 (NUREG 0800),. dated -July 1981, also provides

- -guidelines acceptable to the NRC'for' implementing GDC -3 in -the development of a fire protection' program.. The BVPS Unit 2 Fire Protection System' (FPS) was . designed using. the guidance of Branch Technical Position (BTP)

!- CMEB 9.5-1. BVPS Unit 2 utilizes . alternatives ;to the guidance provided in Branch Technical Position CMEB 9.5-I with the associated ' justifications provided ~in.

Appendix 9.5A of the FSAR.

a. 'A Fire Protection' Safety . Evaluation Report was issued for;BVPS Unit 2 as:part of NUREG 1057,' "SER' Related to the Operation of BVPS Unit 2."

7. The BVPS Unit 1 and BVPS Unit' 2 operating license-establishes the requirement for' implementing and maintaining in effect all provisions of the. fire protection program. Table 1 and 2 of this SAP provides the operability and surveillance -requirements, respectively for the fire protection systems for both-Units 1 and 2.

8. The fire insurance requirements- (Tables .3 and 4) for the fire protection systems were added to this SAPfto provide a single source document where all ' fire protection requirements could be located. .The fire insurance requirements are not ~ to. be- construed as conditions for our operating license under NRC rules and regulations.

B. Operation

1. Fire detection and suppression systems shall be operated in accordance with established operating procedures and instructions.

2. Permanent and portable fire protection equipment shall be operated in accordance with Operating Manual Chapter 1.33 (2.33) -

Fire Protection System, and Operating.

Manual Chapter 1.55A (2.55A) - Operations Surveillance Testing of Fire Protection Equipment. '

3. Permanent and portable fire protection equipment should not be used for purposes other than fire protection.

Page 9 of 64 Revision 4 l

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u m9Dm. - [u m lCluiC(!dCh!pter Nuc1ctr Grtup - Sits Admini2tr:tiva Proc:dur:a C. Maintenance

1. Maintenance or repair of fire protection systems, equipment or elements shall be requested and performed in accordance with SAP 3D, "The Maintenance Work Request."

2. First-line supervisors shall ensure the requirements for transient combustibles, ignition sources, and fire barrier penetrations or barriers are met as described in Maintenance Manual, Section 13.

D. Inspection and Testing

. 1. Table 2, " Fire Protection System Surveillance Requirements" identifies the minimum requirements for periodic testing and inspection that is delineated in the FSAR for BVPS Units 1 and 2.

2. Open flame testing for leak testing purposes is prohibited.

3. Fire rated assemblies and penetration seals are inspected in accordance with approved station testing procedures.

4. Operations testing for fire protection related equipment (33 series) are performed in accordance with Operations Surveillance Tests (OSTs).

5. Maintenance testing for fire protaction related equipment (33 series) are performed in accordance with Maintenance Surveillance Procedures (MSPs), Preventive Maintenance Procedures (PMPs), Corrective Maintenance Procedures (CMPs) and Instrument Calibration Procedures (ICPs).

6. Post-maintenance testing shall be performed in accordance with SAP 8 " Maintenance," and SAP 3D, "The Maintenance Work Request."

7. Operations Qual:.ty Control (0QC) activities that govern surveillance and inspection of maintenance for fire protection related equipment (Category F) are identified in 0QC Procedures.

E. Control of_ Ignition Sources l

l 1. Any activity involving an ignition source shall be governed by a Hot Work Permit in accordance with the i Maintenance Manual, Section 13.  ;

I l

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Nuc12 r Group - Site Administr tive Proctduras r p [pt..[jj'C_haptgp[9D[(,;j .(;.c s L i f(jjj F. Control of Combustibles and Flammable Liquids

1. Control of transient combustibles and flammable liquids shall be in accordance with Operating Manual 1.56B.4 (2.56B.4), " Fire Prevention and Control," and Maintenance Manual, Section 13.

G. Engineering Design and Procurement Document Control

1. Physical modifications to permanent fire protection equipment shall be accomplished in accordance with Nuclear Engineering and Records Unit (NERU) procedures.

2. The control of procurement document reviews shall be in accordance with NERU procedures.

NOTE: Certain FPS valves are listed as Category I (ex.,

Containment Isolation Valves, interconnecting valves to the SWS) and are identified in Chapter 1.33 (2.33) Valve List of the Operating Manual.

3. The Fire Protection System (FPS) is designated as

" Category F" (except as noted above). The special category designation is to insure that the guidelines for design, procurement, installation, testing and inspection and administrative controls for the fire protection system are adequately reviewed and controlled. Operations Quality Control (0QC) activities associated with these requirements are described in applicable OQC procedures.

4. The Fire Protection System was designed utilizing the guidelines of NFPA Codes and based on recommendations from the Fire Insurance carriors.

5. Fire Protection equipment shall conform to the type identified in the list of approved equipment issued by Underwriter's Laboratories, and/or conforms to the guidelines and recommendations of ANI (American Nuclear Insurers) and NFPA Standards for Sprinkler Systems (NFPA No. 13), CO2 Systems (NFPA No. 12) and Water Spray Systems (NFPA No. 15).

6. Design Changes (DCPs) shall be reviewed as applicable per the following:

BVPS Unit 1 - Updated Final Safety Analysis Report (UFSAR) and the Updated Fire Protection Appendix R Review Report (UFPARRR).

BVPS Unit 2 - Final Safety Analysis Report (FSAR) and the Fire Protection Safe Shutdown Report (FPSSR).

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. bI kNi . Md ij [L;; by;d Nuclear Group - Site Administrative Procedures Chapter 9D

7. The BVPS Unit 1 UFPARRR and the BVPS Unit 2 FPSSR shall be administratively controlled and periodically updated as appropriate. Changes to the Reports shall be made per Instructions provided in Attachment A to this SAP.

H. Training

1. Instruction

a. Training will be accomplished in accordance with Training Manual, Section 9.3 " Fire Protection Training," which meets the requirements of OSHA Standard 29 CFR 1910.156(c), 10 CFR 50.48, NFPA 27-1976, and the guidelines established in BTP CMEB 9.5-1,

2. Training Program

a. The training program includes instructions to all station personnel regarding immediate actions to be taken upon discovery of a fire.

b. Fire Brigade members are given regular training and practice in fire fighting and rescue routines, including radiological control practices, evacuation procedures and escape routes, etc., to ensure that each member is thoroughly familiar with the steps to be taken in the event of a fire.

Classroom instructions, with training aids such as literature and other audio and/or visual aids, and practical, hands-on training are provided to familiarize the members of the Fire Brigade in fire fighting techniques and equipment.

c. Fire Watches and Fire Barrier Attendants are provided with initial hands-on training of fire extinguishers, trained in proper fire reporting procedures, and provided with an annual familiarization through the General Employee Refresher Training (GERT) program.

d. Fire Marshalls are given periodic training in fire-fighting and evacuation procedures and escape routes, as appropriate.

e. Training records shall be maintained for at least 3 years.

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. . m - ,- s - . .. 9 Nuclear Group - Site Administrative Procedures I bihil i b b *i thapter 9D

3. Fire Drills

a. Plant fire drills and critiques shall be periodically scheduled and conducted in accordance with the Fire Training Program.

b. Each Shift Fire Brigade Squad will conduct at least four (4) drills per year which will include the use of fire protection and/or first aid equipment.

Each Brigade Squad member will participate in at least (2) drills per year.'

c. Drills will periodically be held on back-shift, will normally be unannounced and will include a critique as well as assessment of equipment and Brigade effectiveness.

d. All fire brigade personnel will participate in a retraining program over a two (2) year period.

e. A site fire drill will be conducted with local fire department participation at least annually.

f. A cable spreading room drill will be conducted by each shift fire brigade squad at least once a year (applicable to Unit 2) . "

I. Prefire Plans

1. Strategies for fighting fires in all safety-related areas and in areas presenting a hazard to safety-related equipment are defined in Operating Manual 1.56B.3 (2.56B.3), "Prefire Plan Strategies." These strategies are not procedures or instructions per se, but serve as resource information to be used for training purposes and by the fire brigade as an aid to fire fighting.

J. Quality Assurance

1. Fire Protection shall be conducted in accordance with Appendix C of the DLC -

Operations Quality Assurance Program.

2. The Quality Assurance program ensures that the guidelines for design, procurement, installation, testing, inspection and administrative controls for the Fire Protection Program are adequately reviewed and controlled.

K. Physical Requirements

1. Qualifications of fire brigade members include physical examinations in accordance with guidelines of ANSI N-546 Page 13 of 64 Revision 4 l

. s" Nuclaar Group - Sita Administrativa Preciduras-

~

~ Chapter 9D conducted every three. years, and an; annual review by the i~ Duquesne Light Company Medical Department jto screen

-personnel for medical disorders..

L. Program Review

1. Audits shall; be conducted utilizing the guidelines of Generic Letter.82-21 and performed under the cognizance

, of the Offsite Review Committee.

, a. The fire ' protection program and' implementing procedures shall be reviewed at least'once per 24 -

months by the QA Unit.

. b, 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 personnel, an outside fire protection firm, QA or American Nuclear Insurers-(ANI).

- 4

c. An inspection and audit of the fire protection and loss prevention program.shall- be performed by. a qualified outside fire consultant or'ANI.at least once per 36 months.

M. Records

1. Records which document compliance with the fire protection program shall be retained in accordance with.

Site Administrative Procedure Chapter -7, " Office, Records Management and Security."

N. Out-of-Service Requirements /Reportability

1. Tag-out of the fire detection and fire suppression

! systems shall be in accordance with SAP 41, " Clearance Procedures." The on-duty shift supervisor. for. the respective unit shall ensure compliance with operability requirements for fire protection. Refer to. Tables 1 and 3 of this SAP . for required actions to be taken for fire protection equipment inoperable.

2. An inoperable or partially inoperable (i.e.E degraded)'

fire protection system or component shall be reported as an impairment per SAP 3B, " Reporting Requirements", and i appropriate actions taken. Reportability criteria of 10 CFR 50.72 and 10 CFR 50.73 should be evaluated for

, applicability. When evaluating the degraded. or

}' inoperable condition, consideration' for a fire event

[ should also be postulated.

~

Page 14 of 64 . Revision 4

?

l!

fi n

E NUCLEAR GROUP - SITE ADMINISTRATIVE PROCEDURES l J il .,: [ 1OLJ.Pd?J 1n 5 0CHAPTER

" O Il Oi!!

SD D If FIRE PROTECTION ADMINISTRATIVE ORGANIZATIONAL CHART.

' NUCLEAR GROUP NUCLEAR GROUP SENIOR VICE PRESIDENT l

SEN60R MANAGER VICE PRESIDENT RR MNAMR NUCLEAR ENGR.  !

NUCLEAR OPERATIONS NUCLEAR

- ANO RECORDS I I I I PLANT NUCLEAR NUCLEAR ENGl#4EERING MANAGEMENT SAFETY

--~

TRAINING DEPARTMENT SERVICES MANAGER MANAGER MANAGER MANAGER MANAGER DIRECTOR LICEN86NG SENIOR ,

UCENSING l supervisor FIRE PROTECTION ENGINEERS LEGEND COMMAND

-- COMMUNICATION FIGURE 1 Page 15 of 64 Revision 4 i

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

NUCLEAR CROUP - SITE ADMINISTRATIVE PROCEDURES

,0unr v- CHAPTERm 90s-

- i i .! ! .. : ,41 di bt.; U w u b ; R_ )f SITE FIRE BRIGADE (EMERGENCY SQUAD) ORGANIZATIONAL CHART FM BRNBADE CPEIF

, NUCLEAR STATION OPERATING FOfEMAN

\  ?

1 FM BRNIADE CAPTAIN 8

NUCLEAR CONTROL OPERATOR ,-

I

/

ADDITIONAL SfMGA.OE M84 3

SegeRNOF'T N 4E_ TOTAL)

- NUCLEAR OPERAYOR(8)

- NUCLEAR gor.MDL QPERATORW)

- SHIFT CHEh48 S) . '

- SHIFT RAD TECF#GCIANOB) i i l lf FIRE MARSHALLS

- QUAUFIED BRNBADE MEMBER (8)

- QUAUFIED DLC SUPERVISOR (8) 1r - .

a i:

BRNBADE ASSISTANTS (

t

'i ,

- COMMANDEERED EMPLOYEECS) ,

j

\

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FIGURE 2 i

/

Page 16 of 64 Revision 4 .

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e TABLE 1 ( Page 2 or 5) y a

SYSTEM REQUIREMENI APPLICABLE MODES CONDailON REQUIRED ACTION TIME REQUIREMENT rs

2. (continued) c. The DVPS #2 Booster Pump At all times. c. Booster Pump i nope rab le.

c. Restore to OPERABLE status

c. Within 7 days. ko (capacity 625 gpm) OR j capable to taking provide an suction from the alternate water i Service Water Sys supply to the m (SWS) se a f igned fire suppression r 1 to the Unit 2 hose rack stations water sys capable g-or supplying for the safety backup vater to >

related equipment areas, the applicable safety related y

r equipment a reas. 3 to n

3. Spray and/or The following Whenever the equip. a. One or more of a. Establish an a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Sprinkler System sprinkler systeas being protected is the selected hourly fire watch Q n

serving areas shall required to be portions patrol in the r bo OPERABLE: OPERABLE. i nope ra b l e in arrected a rea $

m areas conta ining with backup fire

$w Applicable to Units 1 and_g:

redundant systems or components.

suppression capability, y

! o

- Cnet. (HHR Area ) r)

$ - Cnet. (Cable Pen. b. Restore to OPERABLE status.

b. Within 114 days. $,

0 Area ) c

- Aux. FW Pump Area "1

- CCR Pump Area $

os - Ma in f i l ter Bank n

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n SYS T E M REQUIREMENT APPLICABLL MODES CONDlilON REQUIRED ACilON TIME REQUIREMENT 2 M

4. CO2 stem The following 10 lon Whenever the equip. S " Establish a .

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Q (10 ) CO2 Systems shall be being protected s any continuous fire OPERABLE: required to be or e a reas. watch in the m

O PE RABLE. arrected area (s)

Unit 1 A rea s : NOTE. wi'th backup fire ,

- Cable f ray Unit I: '"P P I* * * "

Mezzanine System OPERABLE with capability. r 4

- Cable Vaults min. level of 30% n

- Diesel Cenerator & min. pressure of b. Restore to b. Within 14 days m Rooms 275 psi 9 (n OPERABLE status, associated storage a jU It1 2 Areas; tank, g

- Cable Spreading m Area Cntri. Bld9' Unit 2: M

- I nst rumen ta t ion System OPERABLE with $

Room Ontri. Bidg. min. level of 91% n

- Communication Room & min pressure or

• Cntrl. Bldg. 29s, psig in one of r"

- Cable Tunnel the two 10 ton <

Between Cntrl. & storage tanks. m N

H Aux. Bid 9s. m N

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D Bldg. S

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e TABLE 1 ( Page 4 or 5) 2:

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SYSTEM RLQUIREMLNi APPLICABLE MODES CONDITION REQUIRED ACTION TIME REQUIREMEMy a m

M

' > . Fire liose Hose stations Whenever the equip. One or more selected a. Provide equivalent a. Within I h r. I f' O Stations serving the in the a reas sta t ions inoperable, capacity backup the i nope ra b le 8 following a reas protected by the hose protection station is the C

• O shall be OPERABLE: selected stations is to the unprotected prima ry means required to be a rea , of fire 1 Unit 1 A rea s: OPERABLE. protection in the Primary Aux. Bldg.

Fuel Bldg.

arrected area; otherwise, within n

$ I

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- Service Bldg.

(Safety-Related b. Restore to b. Within 14 days,

>m-A rea s ) OPERABLE status.  %

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( Pipe Tunnel y A rea s ) n

- Containment g i,jn ll_2 A rea s : r

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N m g - Diesel Gene ra to r oo Bldgs. m.

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- Cntr1. Bldg. & m

$ Cable Tunnel

- Safegua rds

6. lialon Systems Halon Systems Whenever the equip, a . One o r mo re o f a. Establish a a. Within I hour, protect ing the being protected is the selected continuous fire following a reas required to be systems watch in the _

shall be OPERABLE. OPERABLE. inoperable in arrected area .I areas containing with backup fire C' *t Unit 1 Areas:

- Process Equipment redundant systems or components.

supp res s ion capability. . "

k +]

Area (Zone 1)

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b. Within 14 days T a

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Nuc1 car Group - Sita Adainistrativa Procedurae 53. g Ch1ptsr c9D .;.s5 r/

4 - -

. l~ 73 7,3 ~ 4 . .

TABLE 1.1 U S 'I U2 '

• FIRE DETECTION INSTRUMENTS - UNIT 1 As a minimum, the fire detection instrumentation for each fire detection zone shown in the Table below shall be OPERABLE:

Instrument Location Minimum Instruments Operable Smoke Heat

1. Control Room 4 N/A

2. Cable Spreading Mezzanine 20 4

3. West Cable Vault 3 3

4. East Cable Vault 3 3

5. Computer Room 1 N/A

6. Normal Switchgear Room 8 N/A

7. A/E Emergency Switchgear Room 3 N/A

8. D/F Emergency Switchgear Room 3 N/A

9. Remote Shutdown Panel 1 N/A (Process Instrument Room)

10. Station Battery Rooms (each) N/A 1

11. Relay Room 1 N/A

12. No. 1 Diesel Generator 2 1

13. No. 2 Diesel Generator 2 1

14. Upper Charcoal Filters N/A 6

15. Lower Charcoal Filters N/A 6

16. Control Room Air Conditioning Room 2 N/A

17. Reactor Trip Breaker Room 3 N/A

18. Primary Auxiliary Bldg. (PAB):

PAB Elev. 735' 5 N/A PAB Elev. 752' 8 N/A PAB Elev. 768' 7 N/A Page 22 of 64 Revision 4

Nuc12tr Group - Sito Administrativa Proctdursa -

f { ,

TABLE 1.1 (continued)

Instrument Location Minimum Instruments Operable '

Smoke -Heat

19. Charging Pump Cubicle 1/ cubicle N/A 20.' Cable Vault 3. -4 N/A (Elev. 720' on side of

-Unit 2 Control Room)

21. Intake Structure-(A, B and C Cubicle) 6/ cubicle N/A1 D Cubicla N/A. 1

22. CCR Pump Area 4 ..N/A

23. Auxiliary Feedwater Pump Area 4' N/A'

24. Cable Penetration Area- 2 N/A

25. RHR Pump Area 2. -N/A

26. Chemical Addition Building -3 N/A t

i.

i Page 23 of 64 . Revision 4 l

i

~ r. . . , , - -

- -. --,e , ,, . . . . .

- r- r-- .> .

Nuclear Group - Site Ad2inistrative Proceduras f khfC,h[ajttr,[9(; i TABLE 1.2 FIRE DETECTION INSTRUMENTS - UNIT 2 As a minimum, the fire detection instrumentation for each fire detection zone shown in the Table below shall be OPERABLE:

Instrument Location Minimum Instruments Operable Smoke Flame Heat

~1. Fire Area CB-1; Control Bldg. 707'

- Zone 11 (Comm., Inst. and Relay 11 Room Under Floor Areas)

- Zone 2-1 (1400) Inst./ Relay Room 13*

- Zone 10 (Inst. and Relay Room) 7

- Zone 12 (MCC Room) 1

2. Fire Area CB-2; Cable Spreading 725'

- Zone 23 (Cable Spreading Area) 12

- Zone 2-1 (1200) Cable Spreading Area 9*

3. Fire Area CB-3; Control Room

- Zone 17 (Control Room) 8

- Zone 67 (Vertical Board) 2

4. Fire Area CB-4; Computer Room

- Zone 18 (Computer Room) 1

- Zone 210 (3400) (Computer Room) 1***

5. Fire Area CB-5; HVAC Equip.

Fan Room 735'6"

- Zone 19 (HVAC Equip. Fan Room) 2

- Zone 20 Fan Room (Duct Mounted) 1

- Filter 2HVC*FLTA252A (2HVC-FD252A1) 1

- Filter 2HVC*FLTA252A (2HVC-FD252A2) 1

- Filter 2HVC*FLTA252B (2HVC-FD252B1) 1

- Filter 2HVC*FLTA252B (2HVC-FD252B2) 1

6. Fire Area CB-6; West Comm. Room 707'

- Zone 14 (West Comm. Room - 1 Ceiling Area)

- Zone 310 (4100) (West Comm. 5***

Room - Ceiling and Under Floor Areas) i I

l Page 24-of 64 Revision 4

.'~ [ (y 5 idMfi ! $ I

.- " D(1 li h @U w s)u d N i I Vt {.

, Nuc1sar Group - Site Administrativa Procedures Chapter 9D TABLE 1.2 (continued)

Instrument Location- Minimum' Instruments Operable Smoke Flame Heat

!- 7. Fire Area CT-1; Cable Tunnel 712'6"

- Zone 16 (Cable Tunnel North) 4

- Zone 15 (Cont. Bldg./ Cable 2

. Tunnel South)

- Zone 22 (Cable. Tunnel South) 4

- Zone 36 (East End of Cable Tunnel) 1

- Zone 2-1 (1300) Cable Tunnel 712'6" 14*

8. Fire Area CV-1; Cable Vault-(West) 735'

- Zone 50 (Cable Tunnel / Aux. Bldg.) 3

- Zone 2-2 (2200) (Cable Tunnel / 9*

Aux. Bldg.).

- Zone 30 (Cable Vault West) 7

- Zone 2-2 (2100)(Cable Vault West) 7*

9. Fire Area CV-2; Cable Vault (East) 735'

- Zone 31 (Cable Vault East) 5

- Zone 2-2A (2300) (Cable Vault East) 4*

10. Fire Area CV-3; Cable Vault 755'

- Zone 32 (Cable Vault) 11

- Zone 2-3 (3100) (Cable Vault) 13*  !

- Zone 52 (Cable Tunnel / Aux. Bldg., 4 j including ASP) ,)

- Zone 2-3 (2400) Cable Tunnel / 6* i Aux. Bldg.

11.. Fire Area CV-4; Cable Vault -

Fan Room 773'

- Zone 43 (Emer. Switchgear HVAC) 2

12. Fire Area CV-5; Personnel Hatch 773' i

.' - Zone 41 (Hatch Area) 1

- Zone 42 (Purge Duct Work Area) 2 i

13. Fire Area CV-6; Relay Room 755'

- Zone 53-(Relay Room) 2

- Zone 2-7'(3300) (Relay Room) 2*

Page 25 of 64 Revision 4

. Nuc1scr Group - Site Administrativa Procedures Ch 9D TABLE 1.2 (continued)

Instrument Location Minimum Instruments Operable Smoke Flame. Heat

14. Fire Area DG-1; Diesel Bldg. No. 1

- Zone 63-(Orange Diesel) 2

- Zone 2-5 (Orange Diesel) 4*

15. Fire Area DG-2; Diesel Bldg. No. 2

- Zone 62 (Purple Diesel) 2

. Zone 2-6 (Purple Diesel) 4*

17. Fire Area FB-1; Fuel Bldg.

- Zone 66 (Fuel Pool Cooling 1-Pumps 739)

- Filter 2HVQ-FLTA227 (2HVQ-FD227) 1**

18. Fire Area MS-1; Main Steam Valve Area

- Zone 44 Main Steam Valve Area 791'6" 3

- Zone 45 Fan Room 773'6" 1

- Zone 46 Compressor Room 773'6" 1

19. Fire Area PA-3; Aux. Bldg.

- Zone 49A (CCP Heat Exchanger 9 Area 710')

- CCP Area (2FPW-FD270A thru F) 3*

- Zone 49B (Aux. Bldg. 718'6") 6

- Zone 51A (Aux. Bldg. 735'6") 11

- Zone 51B (Aux. Bldg. Charging 7 Pump Area)

20. Fire Area-PA-4; Aux. Bldg. 755'6"

- Zone 54A (Aux. Bldg. 755'6" North) 9

- Zone 54B (Aux. Bldg. 755'6" South) 11-

- Zone 56 (Aux. Bldg. 755'6" Duct 2

Mounted) 4 Page 26 of 64 Revision 4-i

. . . , . , - --,n - - - . , . , . - - , -.

Nucle'r

~

a Group - Site Administrativa Procedures F0Fi!ijfeusi;u:O!f0/!

Chapter 9D TABLE 1.2 (continued)

Instrument Location Minimum Instruments Operable Smoke Flame Heat

21. Fire Area PA-5; Aux. Bldg. 773'6"

- Zone 57A Aux. Bldg. 773'6" 6 North (includes Fan Room)

- Zone 57B Aux. Bldg. 773'6" South 11 l

- Zone 58 (Duct Mounted) -1 l

- Filter 2HVS*FLTA205A (2HVS-FD205A) 1**(L)

- Filter 2HVS*FLTA205B (2HVS-FD205B) 1**(L)

Filter 2HVS*FLTA208A (2HVS-FD208A) 1**(L) I

- Filter 2HVS*FLTA208B (2HVS-FD208B) 1**(L)

22. Fire Areas PA-6 and 7;. Aux. Bldg. 755'6"

- Zone 55 (MCC Rooms E03 and E04) 1/ Room

,23. Fire Area PT-1; Pipe Tunnel 718'6"

- Zone 40 (Pipe Tunnel Cable Vault) 10

24. Fire Area SB-1; Service Bldg. -

Emergency Switchgear 730'6" i

- Zone 01 (Orange Switchgear) 12

25. Fire Area SB-2; Service Bldg. -

Emergency Switchgear 730'6" ~

- Zone 02 (Purple Switchgear) 11 26'. Fire Area SB-3; Service Bldg. -

Cable Tray 745'6"

- Zone 4A (Northern 2 Rows) 12

- Zone 4B (Southern 2 Rows) 12

- Zone 2-4 (3200) Cable Tray ~ 13*

Area 745'6"

27. Fire Area SB-4; Service Bldg. -

Normal Switchgear 760'6"

- Zone 5A (Normal Switchgear, North) 10

- Zone SB (Normal Switchgear, South) 7 Page 27 of 64 Revision 4

j ,

('t 3 , '77. ,u_'-

y. t .

.gg;gi t-l [ti D>hapter 96 ; t did

. - l lji ii n , 2 lji.2 6. -

Nuc1str Group - Site Administrativa Proceduras TABLE 1.2 (continued)

Instrument Location Minimum Instruments Operable Smoke Flame Heat

28. Fire Area SB-5; Service Bldg. 780'6"

- Zone 7A (West End) 8

- Zone 7B (East End) 7

- Filter 2GSS-FLTA255A (2GSS-FD255A) 1**

- Filter 2GSS-FLTA255B (2GSS-FD255B) 1**

29. Fire Area SB-6,7,8,9; Battery Rooms 730'6"

- Zone 03 (Safety Related Battery 1/ Room Rooms 2-1, 2-2, 2-3, 2-4)

30. Fire Area SB-10; Battery Room 760'6"

- Zone 6 Battery Room 2-5 1

31. Fire Area RC-1; Reactor Containment (#)

- Zone 64 (Cable Penetration Area) 10-

- Cable Pen. - Purple (2FPW-FD232A/C) 2**

- Cable Pen. - Orange (2FPW-FD233) 2**

- Zone 65 (RHR Pump Area) 1

- 2RHS*P21A (2FPW-FD231A/B) 1**

- 2RHS*P21B (2FPW-FD230A/B) 1**

- Filter 2HVR*FLTA211A (2HVR-FD211A) 1**

- Filter 2HVR*FLTA211B (2HVR-FD211B) 1**

32. Fire Area SG-IN; North Safeguards Area J

- Zone 26 (Elevation 718'6") 3

- Zone.28 (Elevation 737'6" 3 and Duct Mounted)

- Aux. FW Pump (23B) Area (2FPW-FD234A/B) 1**

33. Fire Area SG-1S; South Safeguards Area 4

- Zone 27-(Elevation 718'6") 3

- Zone 29 (Elevation 737'6" 3 and Duct Mounted)

- Aux. FW Pump (23A) Area 1**

(2FPW-FD235A/B)

- Steam Driven Aux. FW Pump (22) 1**

Area (2FPW-FD236A/B)

Page 28 of 64 Revision 4

-u g

• v. , '"

,, 5 .E4

"3

, [ ej { g ,([4 [ C l Li .ii A ,*  !

Nucle:r Group - Site Administrstivs Procedures Chapter 9D TABLE 1.2 (continued)

Instrument Location Minimum Instruments Operable Smoke Flame Heat

34. Miscellaneous Areas:

- Zone 59 (Aux. Bldg. - Elev. Mach. Rm.) 1

- Zone 8 (Service Bldg. Stairwell) 3

- Zone 24 (Cont. Bldg. North 1 Stairwell)

- Zone 25 (Cont. Bldg. South 1 Stairwell)

- Zone 33 (Aux. Bldg. Personnel Passage) 3

- Zone 34 (Cable Vault Personnel Passage) 3

- Zone 35 (Turb. Bldg. Personnel Passage) 3

- Zone 37 (Aux. Bldg. NW Stairs) 1 (EL. 712'6")

- Zone 38 (Cont. Bldg. Personnel 2 Passage 722'6")

- Zone 39 (Control Room 3 Entrance Way)

- Zone 60 (Aux. Bldg. Personnel 1 Passage)

- Zone 47 (Cable Vault East Stairs) 1

- Zone 48 (Cable Vault West Stairs) 1 Table Notations

• Detectors associated with the CO system actuation-circuitry.

• • Detectors associated with the water suppression system actuation circuitry.

• • • Detectors associated with the Halon system actuation circuitry.

(L) Line-type (thermistor cable) heat detector.

(#) The fire astection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.

Page 29 of 64 Revision 4

TABLE 2 ( Page 1 of 11) y n

flRE PROTECTION SYSTEM SURVEILLANCE REQUIREMENTS g' NOTE: Each surveillance requirement shall be pe r fo rmed within the specified time i nte rva l as derened in the Technical N Speci fica tions ( Section 4.0.2) .

a N

CAUTION: Failure to perform a surveillance requirement constitutes railure to meet OPERABILITY requirements. 0-t.

SYSTEM REQUIREMENT SURVLILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) I us H=

1. Fire Detection Instrumentation for each a.1. Each of the rire a.1. 6 months a. OST 1.33.13 Instrumentation fi re zone protecting detection instrmnts. OST 1.33.16 >-

sa fety-rela ted equipment which are accessible (OST 2.33.13) shall be OPERABLE. during plant (OST 2.33.16) D k"

operation shall be Unit 1: demonstrated $'

Refer to Table 1.1 or operable by n this SAP, performing a CHANNEL y FUNCTIONAL TEST. n Unit _2: ra Refer tn Table 1.2 or a.2. Fire detectors which a.2. During each COLD h 3

this SAP. are not accessible SHUIDOWN exceeding f"j during plant 24 hrs, unless y w operation sha ll be pe rfo rmed in o demonstrated OPERABLE previous 6 months, n

$$ by performing a CHANNEL FUNCTIONAL

('

c O

g TEST. g.

o$ b. The NFPA Standa rd 720 b. 6 months b. OST 1.33.13 Class A supervised OST 1.33.16 ci rcui ts supervision (OST 2.33.13) associated with the (OST 2.33.16) detector alarms or each of the fire detection instruments shall be demonstrated

. - T')

OPERABLE.

{a *y

c. The non-supervised c. Monthly c. N/A circuits between-the (All circuits - -+

local panels and the supe rvi sed ) * - " '

Control Room shall be demonstrated OPERABLE.

$5 l d C. .I

• d ,52 n r Nu, ',

g3 n Om> -l O M w.

u3 s- tt$1 n.

C~

{ ,(

wed

__ 'b

TABLE 2 ( Page 2 of 11) 27 c

SYSTEM REQUlHEMENI SURVEILLANCE REQUIREMEN1 REQUIRED FREQUENCY REFERENCE UNIT 1 (DMIT 2) O m.

M

2. fire Suppression a. The fire suppression a.1. Starting each pump a.1. Monthly a.1. OST 1.33.7 Q Water System system shall be and operate on OST 1.33.8 o demonstrated rec i rc f low fo r a t c OPERABLE. least 15 minutes 5 (STACCERED TEST a DASIS). u) -

r <

a.2. Verification that a.2. Monthly a.2. OST 1.33.1 rt each valve (manual, (OST 2.33.1) m-powe r ope ra ted o r p.

auto) in the flow a path is in its  %,

correct posi t ion. A-r a.3. Performance of a a.3. Annual a.3. OST 1.33.4 $

sys ya rd loop and OST 1.33.6 M hyd ra n t flush. (OST 2.33.4) $;

e a.4. Cycling of each a.4. Annual a.4. OST 1.33.12 <

testable valve in

• ny (OST 2.33.12) g3 the flow path. Ms 00 M d a.5, Performance of a a.5. 18 months a.5. OST 1.33.12 S.

us system functional (OST 2.33.12) m test which includes @*

O simulated automatic n en actuation of the G system throughout "

as s- its operating sequence, and:

a) Verifying that ==7 g each automatic valve in the flow (+~~~ Aa}

path actuates to its correct

[C position, -=

b) Verifying that ((* 2[

each pump develops at least 2500 gpm at a system head

(((2-of 250 feet, 7 c.

c). Cycling each f valve in the flow C'9; r4

< path that is not =m e testable during rT<

o plant operation through at least (f m l

~M A one complete "-g*

,, cycle of full t t ra ve l , and (1.z- ,)

en, s ad ,,

mA C

TABLE 2 ( Page 3 of 11) 2:*

C-n SYSTEM REQUIREMENT SURVEttLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) $f m.

M O

?. (continued) d) Veri fying that n O

each high pressure pump starts v (sequentially) to maintain the fire I suppression water un system pressure F' t 9reater than or E equal to 90 psig.

a.6. Performance of a a.6. 3 years a.6. OST 1.33.12 ke flow test of the (OST 2.33.12) H-system ( in accordance f, with NFPA flandbook) m which includes the entire fire loop (Units 1 and 2),

n H-

b. The diesel fire b.1. Verification of the b.1, Monthly b.1. OST 1.33.8 m y2 pump shall be fuel oil day tank Do demonstrated level (greater than n W OPERABLE. or equal to 350 o g, gallons), & starting of the fire pump Q na . p.

diesel engine and c fg operating for at $.

least 20 minutes. m m

b.2. Ve ri fica tion tha t a b.2 Qua rterly b.2. CHM CP 2 DG sample of diesel '9M CP 3 FP.

fuel from the fuel M CP 8 RP-1 oil day tank is g7 within acceptable limits (Table 1 of b.--~ -

ASTM D975-74) when  ;

" 1 ~0 checked for v i sco s i ty, wa te r, . - - - .

and sediment. 7: ,

b.3. Inspection of the fire pump diesel b.3. 18 months b.3 MSP 33.01 *[-

(, ,

MSP.33.02 engine in accordance ,

wi th manufacturer's er recommenda t ions. I' PO lO 5j b.4. Verification that b.4. 18 months b.4. OST 1.33.12 ,{

p. the diesel starts on 33 n auto and operates in for at least 20 ,e-

[*

3 mintues. .

e c~ O

([)

E t

-- c .

e TABLE 2 ( Page 4 of 11) c SYSTEM REQUIREMENT SURVEILLANCE REQUIREMEH1 REQUIRED FREQUENCY O REFERENCE UNIT 1 (UNIT 2) m m

M-

2. (continued) c. It* < e se t fire pump c.1. Verification of the. col. Weekly c.1. OST 1.33.8 0 st ....g 24 volt electrolyte level of E-battery bank and each battery & the c.

cha rger sha l l be ove ra l l battery 'O demonstrated OPERABLE. voltage for each

• i fire pump diesel starting 24 voit battery bank, f3 et m

c.2. Verification that c.2. Quarterly c.2. MSP 33.04 p.

the speci fic gravi ty o.

is appropriate for B continued service of E the ba ttery. r m

c.3. Inspection of the c.3. 18 months c.3. MSP 33.03 $

batteries, to D.

verify that: [

f a) The batteries, G m

'b cell plates & .m

$ battery racks show no visual M

8 02 indication of a W physical damage O-o or abnorma l  %

"* deterioration. & m cn S- b) The ba' te ry-to-battery & terminal connections a re clean, tight, m.

(*g**' .

f ree of corrosion

& coated with 'ClO '

ant i-co r ros ion material. -

--p

d. The DVPS #2 Booster Pump (capacity 625 d.1. Sta rt i ng the Booster Pump and operate d.1. Monthly d.1 (OST 2.33.7) M a gpm) capable of taking for at least 15 min. L.~c ..

wi' suction from the Se rv ice Wa te r Sys.

(SWS) & aligned to d.2. Verification that each valve (manual, powe r ope ra ted o r d.2, Monthly d.2. (OST 2.33.1) {-

C.

the Unit 2 Hose rack L stations for the auto) in the flow *O f safety related path is in its 1

< equipment a reas. correct position. *h?

& ~

CO

% d.3. Performance of a d.3. Annual d.3. (OST 2.33.4) *EI

• • system flush (in ' M ^~'

D conjunction with the d Unit I system flush). f$ )

.T.f.

g-M

_ _ _ _ _. ._ _ . _m . .

TABLE 2 ( Page 5 of 11) f' SYSIEH n

REQUIREMENT SURVEILLANCE REQGFlMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) y p

M

2. (continued) d.4. Cycling of each d.4. Annual d.4. (OST 2.33,12) O n

testable valve in o the flow path. g-d.5. Performance of a d.5. 18 months d.5. (OST 2.33.12) I system functional m test which. includes: r ,

n I

a) Verifying that m the booster fi re >

A-pump develops at least 625 gpm at &

a system head of D 250 feet, 7 n

b) Cycling each M valve in the flow path that is not Fa testable during  %

N plant operation 4 through at least *O

$ one complete cycle of full E

n y t ra ve l , and

{

C o c) Verifying that M the booster fi re @'

e pump maintains e the fire suppression water system pressure greater than or equal to 90 psig, _7s

• e. Fi re Hydrants sha ll *e.1. Hydro test each *e.1. Annual *e.1. OST 1.33.4 C)

-~ .g" be OPERABLE. hyd ran t to verify (OST 2.33.4) * ' "

barrel i nteg ri ty following winter freeze.

7:{*

c .T .

.-r g.

• e.2. Inspection of each *e.2. 6 months *e.2. OST 1.33.4 M

• "' ~s hyd ra n t to ensure (spring and fall) (OST 2.33.4) '

4' hyd ra nt ba r re l s a re dry and threads are I  ;

y l ub ri ca ted. 'g ,

N ',[7]

r .. . 4

, n .. ,

O Pa _

o (m.,.

eg . . . ?

D .. ,

p. .g: * :

• Re f: T.S. Amendment No. 18 ( Fi re Protection SER; dated June 6, 1979) .

,. .9 of =

x em

.r b '

TABLE 2 ( Page 6 of 11)

C d

SYSILM REQUIRLMENI SURVLILL.ANCL REQUIREMLNT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) S.

m-m M

3. Spray and/or The following a reas a. Verification that each a. Monthly a. OST 1.33.1 c)

Sprinkler System applicable to Units 1 & 2 valve (manual, power (OST 2.33.1) shall be OPERABLE: Operated or auto) in Q c

- Cnet. ( RilR Area ) the flow path is in T3

- Cnmt. (Cable Pen. Area) i ts correct pos i t ion.

g

- Aux. FW Pump Area

- CCR Pump Area b. Cycling or each b. OST 1.33.6 U2

- Ma in F i l ter Bank testable valve in the riow path.

OST 1.33,12 OST 1.33.138 m

(OST 2.33.6) y, (OST 2.33.12) p.

(OST 2.33.138) ((

c.1. Performance of a c.1 18 months c.1. OST 1.33.12 hb system functional OST 1.33.138 8 test which includes OST 1.33.21 ((

simulated automatic (OST 2.33.12) m actuation or the (OST 2.33.13B) system. and: Q (OST 2.33.21) <

m y a ) Veri fying that m

on the automatic -n o valves in the O g, flow path actuate $

on to thei r correct m. -

g pocitions on a  %

m manual test m signal, and m os b) Cycling each valve in the flow path that is not testable during _,y plant operation * .

through at least ($"?J one complete ~ -4 cycle of full

t ra ve l . ,,

~

c.2. Inspection of the c.2. 18 months c.2. OST 1.33.130 -

dry pipe spray and OST 1.33.21 "1.

sprinkler headers (OST 2.33.130) ("

to veri fy integ ri ty. (OST 2.33.21)  ;

c.3. Inspection of each c.3. 18 months c.3. OST 1.33.13B I po nozzle's spray a rea OST 1.33.21 *Os

• • to verify the spray (OST 2.33.130)

• t E[

(( pattern is not (OST 2.33.21) [ t ..

m obstructed. ,g,

• (".

so

g. C3' 4

.n s .

-' i

TABLE 2 ( Page T of 11)

SYSILM n

RLQUIRLMENT SURVEILLANCE REQUlHLMLNI REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) y m

N.

3. (continued) d. Performance of an a i r d. 3 yea rs d. BVT 1.33.1 Q flow test through each BVT 1.33.2 o open head spray / (BVT 2.33.1) sprinkler header to {

verify each open (BVT 2.33.2) i nozzle is unobstructed. g e

is. CO2 System CO2 Systems serving the a. Verification of the a. Weekly a. OST 1.33.9 (10 Ton) following areas shall be associated 10 Ton CO2 (OST 2.33.9) >

OPERABLE: storage tank level &

pressure.

g r

2 Unit 1 A rea s: b. Verification that the b. 18 months b. OST 1.33.13A 7

- Cable T ray Mezzanine system (valves and (OST 2.33.13A) n

- Cable Vaults associated dampers) N

- Diesel Generator Rooms actuates manually &

automatically upon Unit 2 Areas: receipt or simulated j

• d - Cable Spreading Area signal.

'* Control Oldg. 48

$ - Inst rumentation Ro >m Control Oldg.

c. Verification of flow from each nozzle

c. 18 months c. OST 1.33.13A o n

(OST 2.33.13A) y - Communication Room during a " puff test".

[

Control Bldg. c.

o - Cable Tunnel Between N

• Control & Aux. Oldgs.

os

- Cable Tunnel Aux. Bldg.

• - Cable Vault & Rod Control A rea s

- Cable Spreading Area Service Bldg.

- Emergency Diesel . . _

Cenera tor Oldg. Room 4';

I G

. p 5

y +.

e f

en P"

N a

5

r g u ~m p g 'O C4 su M

& O

N O

U (' - g n c 0'

_ ."'W r i

~.: ,

TABLE 2 (Page 8 of 11) :a C

SYSI[M REQUIREMENT SURVEILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (GNIT 2)' O '

m-W M

S. Fire Hose Hose stations serving a. Inspection of the fire a. Monthly a. OST 1.33.2 O Stations the following areas shall hose stations (OST 2.33.2) 'oc be OPERABLE: accessible during I plant operations to "O l git 1 Areas a s su re a l l required

• g

- Prima ry Aux. Bldg. equipment is at the j - Fuel Bldg. station. .Mg

- Intake Structure n

- Service Bldg. ( Sa fe ty- b.1 Inspection of the b.1. 18 months b.1. OST 1.33.2 m Rela ted Areas ) fi re hose sta tio.is (OST 2.33.2) >

- Sa fegua rds Bldg. (Pipe not accessible o.

Tunnel A rea s ) during plant B

- Containment operations to assure aIi required equip.

W Un i t 2 A rea s: is at the sta tion. M '

y

- Fuel & Decon Bldg. n

- Diesel Cenerator Bldgs, b.2. Removal of the hose b.2. 18 months b.2. OST 1.33.2 03

- Cable Vault Areas & for inspection and (OST 2.33.2) r Relay Room re- ra c k i ng . <:

y - Service Bldg. m m - Aux. Bldg. b.3. Inspection of all b.3. 18 months b.3. OST 1.33.2 m-00 - Containment gaskets & replacing (OST 2.33.2) N 88 - Control Bldg. & Cable any degraded gaskets @

w Tunnel in the couplings. m i

N - Safeguards A-o c.1. Pa rt i a l opening of c.1 3 years col. OST 1.33.2 5 rn each hose station (OST 2.33.2) m valve to verify #

$ va lve operabili ty &

no flow blockage, c.2. Performance of a c.2. 3 years *- c.2. OST 1.33.2 hose hydrostatic (OST 2.33.2) test at least e q 50 psig above max. *NOJX:

fi re main operating All hoses stored in ( W' v p re s su re , heated areas shall be [ [].

hyd ro-tested at least -

overy 3 yea rs. All e -

hoses stored outdoors =

^

or in unheated building $

a rea s sha l l be hydro-tested at least every C _"

18 months. --

r

{

m -e 0

7

• n O h-g y

• n

s ( .e r

a "Ref: T.S. Amendment No. 18 (Fire Protection SER; dated June 6, 1979). '

(-

~

FS

w. -e

.g

e . .

TABLE 2 ( Page 9 of 11) h*

c SYST[H n ltLQU I RE MEN T SURVEILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT I (UNIT 2) H m

'W M

6. Halon Systems Halon Systems protecting a. Monthly a. OST 1.33.20 the following areas shall

a. Verification that each valve (manual, power $

O be OPERABLE: operated or auto) in c the flow path is in # "

Unit 1 Areas: its correct position. 1

- Process Equipment Area (Zone 1) b. Veri fication of Ha lon b. Semi-annual b. OST 1.33.22 m i

- Process Equipment Area storage ( tank weight (OST 2.33.18) "

(Zone 2) greater than or equal m

- Cable Tunnel (CV-3) to 95% or rull cha rge ) >

weight ( o r l eve l ) Sc Q-Unit 2 Areas:

- Control Bldg. Computer pressure greater than or equal to 90% or k

s Room

- Con t ro l . B l dg . We s t Com.

rulI cha rge pressure, p-n Room N

c. Verification that the c. 18 months c. OST 1.33.23  %

system actuates (OST 2.33.20) e-4 manually and m automatically upon 8 m receipt or simulated m

$ actuation signal. Q n

La d. Performance of a flow d. 3 years d. BVT 1.33.3 m-o test to assure no (BVT 2.33E.1) @

blockage. N m o Os W

F t

D m

t Nd A  ?*g

( , '1 N -

n ,

" , 7

< 7 -4a V- "

C *

.n m

O e n E _: e A e . cs e- _.u

(, _ '

W .w .

b W4s%

-.g .

. q:

. ) ) . .

hcfMWn C@e3 ,9 UpO pcB y r#w Qe"7W ynOSoCN m 7 )" ] ..'wp2*

F 3

r'js t.

9 ~~ ~" 7 , m.r i OU 'n A s.

.~ .~ E C e I; a *

' 4

. " ( [1 '. 'r e '

8' Y

• )

2 ,

) ) ) , r 2 r T 5 5 5 2&o &o I

5. 3 - o 1 o N 5. 3 5. 3 11D 1D U 33 33 33 - - 3-( 31 e L1 e 3.1 3.1 3.1 ) Lr r) 5 ,4is L f g3 L ,4is 1 1 1 1

- .- - f g T - - - 5. 3 3

. ," Lo 4 " o I 1 1 1 33 , L N 1 . 1 . 1 . 421 521 U 2 2 2 3. 2 E

1 T

1 T

1 T

1 T

5.11k211k 1

c c

C TV TV TV TS 34eM34e N VB VB VB SO MLLhOLLh E B( B( B( O( OOOC(OOC R

E . . . . .

F 1 2 3 1 3 E . .

R a a a b b Y )

C s N r E u U

• o Q l h E a R s s s u 4 f h h h n 2 t t t n (

D n n n a E o o o - ly R m m m i I

m i U 8 8 8 e a Q 1 1 1 S D E

R . . . . .

1 2 3 1 3

)

a a a b b 1 s 1 n e l o n ,

e T f d .s ol db inn o n sr f N o h e & neog tu ia e st i i e ei e o E e c t h fll snh t e p gh f tr M hs aea tcl inr asnoal euts a honc ai 0 E ted eri aaa taodia ea c ie d t itd hf 1 R ce ic ecfah av %sh oewg a dsae t s e

I U

fat ffo f iorcer f0 s ru nrr pneaog fl ol r d i ofa o/s ofr t cgao1f ool i net g Q rr ws ot)etne ons ilh e hc&u oku n P

(

a E R

nu ose.

i ry in&e noa.

od n

o%eaeer i0l cl nnad doaeihonm cpral

,nl c

ninptTi ointpced oatnld iioc&me n

sr q icol o tohai al tcs L tdil ti r t1 ei aeautoya tcsnaan ttei cniii.

2 C cefb cwr a c ( nd ppm o cit r c ermu casne. iuwrvd E

N A

es pohe m e p ew e pd et psehl aao a e pprf e t t .el%raro pi h e e pl0aeof emaahs poehtr ihrces f tre L L spcs srmr sapca nesdcndsa1 ppn stl c o rcoepo B t nxas niaa neyecfnbrndaeanh p pb s nueefo eaol ul A l I eea Ifdh I l tmsII aaiaepmisaaaai I armod Vedesc I E V . . . . .

R 1 2 3 1 2 U . . . .

S a a a b b s .

s d e e , )

ie.

) eg f c s g l2 stn a i r l l s rai sevyo n a&

b gs el tt rel o i h mneieanoidbd p s1 eirrrratf m i&

T sl ur ad geeep )s N sisaypntansrr sst E aeobteun isii&lli M cl esdanl aff aan E d/cef etia ( eeeU R ernrarrrhed ,l ss(

I toeiso otsessb U ao f f pi tnwannE Q rl y gsomwl aoocooL E

R farna e,thtrnsw r

reies i nal rid eaisaaR tn,ttA iib is taaomo&rrwrrlE fl eor ied i t etiP ll aetttafeepetO l abd pr r s u e nrmnn l w a n ei o yh r n ei a e e e A(c a s f p s s ai pf d p v b rs en M io t ri i rt S aa Y Br S t ee rn ie fP 1

op tu k j n [ ogpg Uy

[o8 g p

TABLE 2 ( Page 11 of 11) -a 7

n SYSTEM RLQUIREMENI SURVLILLANCE REQUIRFMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) g'  ;

m I n

T. (continued) b.3. Verification that doors wi th automatic b.2. Daily (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) b.2. OH 1.54.3, L3-1-2,- k hold-open & release OL3-1-2,"L4-1-1 & O' mechani sms a re f ree OL4-1-1 Fire Door Check" Logs or obstructions. (OM 2.54.3. L3-1-2, 8 OL3-1-2, L4-1-1 & u)

OL4-1-1 "F i re Doo r H Check" Logs) E[

o.

9 H.

D H-M M

M n

>'=

4 M3 0

DQ ts o k

n C

C O,,

g Os E

S-

~.q

. C ':3 h.' /4.

fa4"-gT-F+7&gg Cb

%d - :a.e h

C~1; '

W n t$ 7 4 " - mi H v.

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TABLE 3 ( Page 2 of 10) -

n D-*

SYSILM RLQUIRLMINI APPLICABLE MOOLS CONDlilON REQUIRED ACilON. IlME REQUIREMENT $

n

?.a. Fire Suppression Operable flow path At all times. flow path inoperable Restore to operable Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. O Water System to non-safety n status o (Applicable to Units 1 & 2 related areas. OR Provide backup fire

.j and Out-Bldgs.) suppression to 8 affected a rea m OB r Establish an hourly "

fire watch patrol

• to affected areal s). >

n.

H r-D

? . b . Ya rd Area f i re Hyd ran t s The fi re hydrant shall be operable At all times, a. One hydrant i nope ra b l e.

a. Operations / Brigade personnel

a. N/A $

n and associated and associated hose cognizant of y llose Cabinots cabinets & ca rt status in event n-and Ca rt Houses houses properly of fire in r (Applicable to stocked, a f fected a rea, Mi Units I & 2 h 8 and Out-Bldgs.) b. Any two (2) b. Provide backup N

b. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

$ adjacent hydrants i nope ra b le.

hose protection o to affected n

$ a rea (wea ther permitting)

[

o c

• OR N Establish an @

hourly fire watch 8' patrol for affected area (s).

O C D

O

" T*.9 Y re.

.h

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$Nt*

1 ABLE 3 ( Page 4 or 10) $$

c o

H SYSTEM j HEQUIRIMENT APPLICABLE MODES CONDlil0N REQUIRED Acil0N TINE REQUIREMERT (D g

et

3. ( con t i rtued ) Comm_on Faci 1itich O

- ERF

- Of fsi to Wa rebotise M

o' C

- Simulator Bldg "

- Waste Hdig. Bldg. 1

( Swi tchya rd ) m

. Site Engr. Sidel. r

.. Pa i rit Shop N'~Wa rehouse C & 13 '

g'

. *^

o..

B H

- [ ,. p g i un rt e' &# n %. .

w - r1

+x  %

pg

,T4:

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^ <

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p A,s

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n CD k CL t-O -

,C, m fD

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c MW%

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4<'

w- #

f. -

em .,

ara r- ,g M= gh er,.,- #

-we d-N e se a(

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~i

• e TAliLE 3 ( Page 5 or 10) f C

-n W

SYSIEM REQUIR[MENI APPLICABLE MODES CONDITION REQUIRED ACil0N TIME REQUIREMENT m ca r .t*

is . CO2 System The following CO2 Whenever the equip. CO2 System Establish an hourly Wi thin is hours, o Systems nerving being protected is inoperable for any fire watch patrol "y non-sa fety related ope ra t iona l or o f the a rea s. In the arrected e a rea s sha I i be required to be a rea ( s ) to check t ope ra b le : opercble. fo r p' rope r coo l i ng , -

no oil leakage, or Unil 1 Areas; any abnormal M- 4 Tiu rb i ne/ Gene ra to r conditions.

• Area (5 Ton CO2 fD System) p

- Gua rdhouse o.

(D.G. floom) s D

0 U_nlil_2.A rea s:

- lu rb i ne/ Gene ra to r {

n Area (7.5 Ton C02 et System)

M Common Fecilitles: 4 ed IlRF Substation m su Bldg. *d 00 - LRf Black D.C. "

" Didg.

> S t,11 0

O C "1

P% O Os a

M C

~

6 h- .,

mv .

he

&? .I aw -

.C n i #

< 7 m g *c o 54 r k~

h eg w

ma.n C' f

_ mm.am m m M > m-C" Y% ' _q ism

_a

e T ABLE 3 ( Page 6 of 10) 2:

8 e

to SYSTEM ftLQU I RE ML N T APPLICAB T MODES CONDITION REQUlftED ACTION TIME REQUIREMENT m n

). O Fi re llose llose sta t ions Whenever the equip. One or more selected a. Provide equivalent a. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. n Stations se rv i ng the in the a reas stations i nope ra b l e . capacity backup C following non-safety protected by the hose protection o

. re l a t ed a rea s selected stations is to the unprotected shalI be operable : operationa l or a rea if the I required to be inoperable station en p

Unit 1 A rea s: ope ra b l e . is the prima ry *

- Turbine Oldg. means of fire m

- Wa rehouse Area protection in the

- Water T rea tment *

- Aux. Bo i 1 e r Rm.

a f fec ted a rea. g Of? E3

- Gua rdhouse b. Establish an b. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. M hourly fi re  %

Unit 2 Areas: watch patrol fo r m T urbine I 13tdg. the affected

- Condensate a rea ( s ) .

Q o

Polishing Bldg. "

- Waste llandling Bldg. 7 (D

'N - Health Physics y

, A rea n is - SOSB C n

$ Common f ac i lit.ie_.]

- Admin. Bldg.*

C-Q - ERI

- Ol'rs i te Wa rehot se m

m m - Waste llandling

~

• BIdg. ( Swi tchya rd )

i< >J

=

e, -3 w -

e .

R, y

xt ," n y

m c

$ (y $

m ~ . n

& w m j

(

.,l '

C

• NOTE: Denotes areas where primary mea is of fire protection is fire hose racks.

c

(, '

~

Ww p.

TABLE 3 ( Page 7 of 10) 2 c

n H

SYSILM RLQUIREMEN' APPLICABLE MODES CONDITION REQUlitED ACTION TIME REQUIRCMEllT m m

-n G. Italon Systems llalon Systems Whenever the equip. a. One o r mo re o f a. Establish an a. Within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.

protecting the being protected is the selected hourly fire watch Q a

following non-safety ope ra t i ona l or systems patrol for the c r ela ted a reas requi red to be i nope ra b l e. room whenever 'O shall be operab e. ope ra b l e, affected room is I unmanned.

Unit 1 A rea s:

- Cua rdhouse (CJ S) n

- Wa rehouse ( Eqt ip. 8 l&C Room) lp.

O.

U! Jtil 2 Areas:

- Computer Room k u

- PAf ( SAS) 7

- PAF ( Te le. n Equip. Rm.) M

- SOSB ( Reco rd s Rm. )  %

- SOSB (Comm. Ra . ) r

- (D 4

m OtikB.I slm m - ERf (Comp., C(mm. Ms M Equip., E.D.'s

" Orrice, EOF, o o

si Records Rooms and 2 N

o ISC Subfloor).

- Simulator Bids, $

n m ( Simula tor, Cc mp. 8 and Records Itn . )

d - Admin. Bldg.

(Records Room)

C )

w 3 a N ,

hs- y SC$

{

C -

F.dI:

x es. 5L

~, ,9 4  %

W "O (0 e,~ , er

,4r E. ._ -

m O q m.

.3 c_ _. _ c

([

,y 4 .

nx

=

• I ABLE 3 ( Page 8 of 10) b c

n

- Ed SYSTEM REQUIREMEh! APPLICABL E MODES CONDITION REQUIRED ACil0N TIME REQUIREMENT @

et

1. Fire Barrier All f i re rated At all times (unless One or more Establish an hourly Within la hours. ,0 3

Pene t ra t i ons assemblies maintenance is being i nope ra b l e . fi re wa tch f'or o separating non-sa fety performed on the the af fected a reas j related fire ar'3as, equ ipmen t/a rea wheneve r .the and all applica3te protected by 002 or a ffected areas I.

penetration sea ls Halon which requires a re unmanned. g

( i nc l ud i ng f i re the fire system r doors, fire darraers, to be 0.0.S.) et etc. ) associate 1

• with a reas protected  ;>

by total floodiqq g-CO2 or Ha lon Systems r shall be operable: D r

Unit 1: $

- Gua rdhouse (D.G. M Room CO2 System) $

- Gua rdhouse (C AS H-Room Haion System) m - Wa rehouse I&C $

D Equip. Room (laton N

$ System) o o

b co !Lnit _2 $,

- Computer Room c o (Halon System) M

" - PAf ( SAS Room cn Halon System) $

A - PAF (Tele. Eq ij i p .

Room Ha lon Sy stem)

Common faciIitits

- ERf Substatioi &

Diach DG Dldgi.

(CO2. System) -

3-

- ERf (Ha lon Sy stem)

- Simulator Did 3 bm )

(Halon System l ,['; y

- Admin. Bldg.

(Records Room) -

- SOSB (Records Room --

Halon System) 1,, . '

- SOSD (Comm. R t. k Halon System) Q

c 7 O e - 3" p

s 4

• O g - rt r .- O o su- -- M U w, m V

~

W C' *

++.a

_ . _ . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ **T"

_ . . . _ _ . ,_ ._m . .

1ABLE 3 ( Page 9 or 10) n W

SYSifM RLQulRLMENf APPLICAtlLE MODES COND1110N REQulRLD AC180N IIME REQUIREMENT $

r1

s. f oam System f'or the Aux. Bo i l e r The foam system shall be ope rab i c.

Whenever fuel oil s to red in tank.

The foam system i no pe ra b l e .

Ensure portable foam eductor wi th Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. kO ruel Oil S to rage adequate foam supply j lank (Unit 1) (at least 50 gal.)

a va i l'a b l e in roam I house, m

r rt (D

o.

B' s

a r

CO .

rt

. rg -

'N ct e

tD M

'N N 00 M (D O O

& fD

@ A*

C O M P9n (D (0 '

F

, k C

~<

3 ses ,

l s

p, C'.

04 %

C~ ,.-

• • s x n e, . -

<D

< {

r O

n.

=,,

e -Q

(. "

a .

t_ g C

EU n... ,

3-Sitt-e

~:.:;*

. - . - --._ __ . -- _. _ . .,. -. , . , - = --. .

9 1 ABLE 3 ( Page 10 or 10) .'

n H

SYSILM HEQUlHENLl4T . APPLICABLE HOOLS CONDITION HEQUIRED ACTION TIME REQUIREMENT $

M

7. Fire Extinguishers fire extinguistiers At all times. Fire extinguishers Replace fi re Wi thin 284 hours0.00329 days <br />0.0789 hours <br />4.695767e-4 weeks <br />1.08062e-4 months <br />, o

n >

(Applicable to shall be operalile inoperable or extinguisher with O Units 1 & 2. and and in their missing f rom equivalent size and .$

Out-Bldgs.) designated designated type, locations. location. I in

' Pda rt t m cL B^

a.

fn rt '

M Da

. rt I

4 Da T (J O n

u m +

O C

O n g- 4 Ch i >

ci

' Gr g.

ed

(* !

k k % s_;

f* g 4

.{' w. .f '

%1.

~  ;,-f y.

1 gn ev g

[

a

( ."

~

M e

k d

.{N Of4 MM c, y

1

- -- ~ . .

T ABLE la ( Page 1 of 10) 6:

C FIRE INSURANCE (ANI) SURVEllMNCE REQUIREME NTS FOR FIRE ' PROTECTION SYSTEM $

m m

SYSILM RLQUIRIHlNI SURVElLLANCE REQUIREMINI "'

REQUIRED FREQUEtLW . REFERENCE UNIT 1 (UNIT 2) o et .

O C

i 1. Fire Detection instrumentation for each a. Each of the fi re a.1. 6 months

• a.1. Unit 1(gl: 'O ~

a ns t rtimen ta t ion fire zone protecting detection instruments OST 1.33.16 g non-sa fety reI a ted and the supervised (OST 2.33.16) equipment shall be ci rcuits associated CA j

ope ra b l e. .#

With the detector a.2. Annual a.2. Out-Bldas : n alarms shall be OST 1.33.28 m

!Lnit_1: demonstra ted operable.

-3

- Gua rdhouse o.

- Alternate Access Iacility  %

p r.

Unit 2: to

- SOSS n

- PAF $

n Out-Q[d_gs d 9 T[ R t Sub. B109 Y.

- Black D.C. Didg.

y - LRF y o - Tra ining Dicg. O

- Simulator Bldg.

n u

• y - Was te tid ig. Bldg. o.-

- Admin. Bldg. C

O

- Meteorologica l Shelter g.

us Ch k

C '))

2

~ .

G"*-g ,

V'.*,,

.C-a "t

.E ; $

m a ns, 5 g 46' ,a yn

-p a

~

O , p . .s n-Q  :- ,

m D~

u. c

.i- ~~

w: '

~l p.,%

'T A

• e TABLE 4 ( Page 2 of 10) .

O H

SYSTEM REQUIRfN[NI SURVLILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) $'

n c1 M

2.a. fire Suppression Operable flow path to a. Verification that each a.1. Monthly a.1. Unit IfU: o.

Water System non-sa fety rela ted a reas, valve in the flow path OST 1.33.1 (Applicabic is in its correct .@

to Units 1&2 position.

(OST 2.33.1)

I and Out-Didgs.) a.2. Qua rterly a.2. O_ut-Bldgsa m OST 1.33.26 * -f n

b. Cycling of each valve b. Annual *

b. OST.1.33.12 in the flow path. (OST 2.33.12) >

OST 1.33.26 y e

a

?.b. Ya rd Area The fi re hydrants sha ll a. Veri fy ope rabi l i ty of a. 6 months a. OST 1.33.4 7 F i re ifyd rants be operable aiid associated hydrants and ensure (OST 2.33.4) n and associated hose cabi iets and c rt ba rrel s a re dry and M Hose Cabinets houses properly st sked. th rea d s lubricated. $

and Ca rt Houses H-(Applicable b. Performance of a b. Annual b. OST 1.33.4 @

m to Units 1&2 hyd ran t flush test (OST 2.33.4) p and Out-Bldgs.) and verify barrel N 00 i n tog ri ty.

u E n-u c. Inspection and c. 6 months c. OST 1.33.5 @,

N inventory of' hose (OST 2.33.5) c o cabinets and ca rt M m houses. m m

CD ...,

6%. + %,)

.$, . ' ~*

r-.;

• 7m' N . 3*

4 =

4

: 3" g ..

a c ,

e 2 e r+-

e C'

q  %

n- -

• e Id TABLE 4 ( Page 3 of 10) c n

H

. - - _ to SYSILM RLQUlilEMENT SURVEILLANCE REQUIRLMENT REQUIRLD FREQUENCY REFERENCE UNIT 1 (UpilT 2) y a

M

1. Spray and/or T he fo l lowi n<l wa te r a. Verification that each a.1 Monthly. a.1 Unit Ifal: O Sprinkler System sprinkler systems valve in the flow path OST 1.33.1 5 serving non-safety is in its correct (OST 2.33.1) I related a reas sha ll be position, operable: a.2. Qua rt e rly a.2. Out-Bidos : ' M r

OST 1.33.26 n_

Unit 1 A rea s : (0

- Turbine Bldg. b. Cycling of each b, Annual b.1. Unit 1121: p (Mezzanine and testable valve in the OST 1.33.6 A.

basement floors) flow path. OST 1.33.12  %

- 112 Seal Oil Unit (OST 2.33.6) p

- Lube Oil Reservoir (OST 2.33.12) M

- Lube Oii Storage Room "

y'

- Aux. Boiler Room b.2. Out-Bldgh: n

- Main Steam Pipe Chase OST 1.33.24 D (opening from Turbine "

Bldg.) c. Performance of a sys. c. 18 Months c.1. Unit 1(21: 4 y - Wa rehouse Area functional test and OST 1.33.12 O ca - PCA Machine Shop verifying that automatic (OST 2.33.12) m 00 - Clean Shop valves in the flow N d - Chemistry Lab path actuate c.2. Out-Bldgh: O vi - Cua rdhouse co r rec t ly. OST 1.33.24 (D W - Yard Area T ransformers 4 g

O M m Unil 2 Areas:

~

fD

, - Turbine Bldg. "

e (Mezzanine and basement floor)

- H2 Seal Oi1 Unit

- Lube Oil Re se rvo i r 7

- Main Steam Pipe Chase

- Pipe Openirig to Waste C -.

")

3' Handiing Bldg. *"

- Condensate Polishing Bldg.

- Waste Handling Bldg.

E n

]

- llealth Physics Bldg.

• s r

- SOSB (~

- PAF J

- Do s i me t ry Ei l dg . m.

- Sc hne ide r/ Cons t ruc t ion B1dg.

j

=e/

- Ya rd Area I ransformers g

, x

.g C C g 2n 2- n e

p ps t3 s' g e

ee h

_ _ a

TABLE 14 ( Pago la or 10) 2

-c O

H SYSibt li[ Qu iTIEMEN T SURVEILLANCE REQUIRLMENI REQUIRED FREQUENCY REFERENCE UNIT I (UNii 2) .g n

-O

.l . (continued) Common faciliLies: M o

- ERf C

- Orrsite Warehouse ."

- Simulator Bldg. I

- kaste llan11ing Bldg.

(Switchyard) g

- Site Engr. Bldg. r

- Faint. Sho, "m

- Wa rehouse C&D

. a. t n

H 03 n

M N

n W

4 m

D N '

. 0Q M se O O

Os LD -

F C.-

C O M eta m 03 V

~:n wl.

m..,,

Gh'a,

,4m W*wwgY .

en u, F9.- ,

e N.' .in g W-'S  %, y

, c.

g ..'.

7;-

er >. ,

M+,

gr A *.

em

• -< ar y u

W C

a s

. y, GB c m W "

O n - c

, :C. ' ' e

=r ,

ju - .,

hi'

?

i_____ _ - _ _ i-- -ee _ _ _ _ _ _ _ _ _ _ - - ,-_

e TABLE 4 ( Page 5 or 10) Z.

c n

H SYSTEM REQllREMLNi SURVEILLANCE RLQUIREMLNi REQUIRLD FREQUENCY REFERENCE UNIT 1 (UNIT 2) @

n O

's. CO2 System the following CO2 Systems a. Verification of the a. Weekly a. OST 1.33.9 . o serving Nor -Safety Rela ted CO2 storage tank level (OST 2.33.9 c Areas shall be operable: & pressure. "

I Unit 1 A rce s: b. Verification that the b. 18 months b.1. Unit 1(2): m

- Iurbine/Cenerator Area system actuates OST 1.33.10 r (5 Ton CC2 System) manually and (OST 2.33.10) re

- Gua rdhous e ( D.G. Room) automatically open m receipt or simulated b.2. Out E dgs : >

_U_q i t 2 Area :

- lurbine/Cenerator Area signal. OST 1.33.29 y r

(7.5 Ton CO2 System) c. Performance of a c. 18 months co l. Unit 1121: c-Common rac_jiities:

" Puff Test". OST 1.33.138 (OST 2.33.138) 7 rv

- Litf Substation Bldg. M

- err Blac) D.C. Bldg. c.2. Out-Bldqh : $

OST 1.33.29 r O

A N 00 N te O n

un O Ut A.

o E m m W

%A ,.

e. lC '

.m) w

[$

V

~

C>

?$ -  % n 0 *:

., ?

7 4 es+. T cu

>*=

A

- m O e" ' n c

(' D e

W. 4 m.,

g

_. . . . . .. _ . . _. _ .- . _ . _ _ __ ._ _ . _ _ .- = ~ _ . . ~ . .-

e TABLE 4 ( Page 6 of 10) 2:

C o-H-

SYST E M REQillREMENT SURVEILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) 8 n

O S. Fire llose Itose stations serving the a. Inspection of the hose a. Annual a. OST 1.33.2 o Stations following tion-safety stations and associated (OST 2.33.2) C re la ted a rea s sha l l be hose. Inspection of 5 i ope ra b l e: all gaskets and

• Ote.t-B l da s . : I replacing any OST 1.33.25 Unit 1 Aress:

- Turbine I.ldg.

degraded hose or gaskets, y

n

- Wa rehouse A rea fD

- Wa te r T re a tment b. Partially opening each b. Annual b. OST 1.33.2 :p.

- eux. Boi er Room hose station to verify (OST 2.33.2) 4

- Cua rdhou: e va l ve ope ra b i l i ty a nd no flow blockage. Out-Bldgst:

m

!Lnit_2 Are;s: OST 1.33.25 *

- iirbine 1.idg.

- Co.idensat e Pol i shing c. Performance or a hose c. 3 yea rs

c. OST 1.33.2 N:

Bldg. hydro test. (OST 2.33.2)

- Waste Itaidling Bldg.  %

.r

- Health Plysics Area Out-Bldgsm : 4 y - SOSB OST 1.33.25

• gn N 00 Common fac lities: M M - Ad m i ,:~ N dg. O

, vi - ERf G-m - Orrsi te ra rehouse A-g o - Waste Hardiing Bldg. n m ( Sw i tchy rd ) m ,

e 9-

' ( i

- ;f i

s 47-1 St A

+

4-.

m.

Q E

.c me-

{

. n.

U .-- m O ( .~.

, o a .o -

p C:: t3 p

] n.;

. sc ;;

p ... ,

_. .. -. - -- .. .. . - -- _ -- - . _ - - _ _~ -

e TABLE 4 ( Page 7 of 10)

[.

o W

SYSIEM REQulRLHENI SURVEILLANCE Hl.QUIREMENT REQUIRED FREQUENCV REFERENCE UNIT 1 (UNIT 2) $

n O

N ti . Halon Systems Halon Systeas protecting a. Verification that each a. Monthly a. OST 1.33.20 0 the folIow ng non-safety valve in the riov path (OST 2.33.18) 5 rela ted a re a s sha l l be is in i ts correct ope ra b l e , position. I to Unit 1 A r_ej s: b. Verification of Halon b. Annual b. O_t J t-B l dqs a : W

- Gua rdhout e (CAS) storage & weight (or UST 1.33.27 E

- Wa rehouse- (Equipment level) & pressure.

I&C Room, >

c. Verification that the c. Annual c. OST 1.33.23 $"

l Unit 2 Areas: system actuates (OST 2.33.20) W I

- Computer Room manually and

- PAF (SAS automatically upon Out-Bldgh:

En

- PAF (Tele. Equip. Rm.) receipt of simulated 651 1.33.27 "

- SOSB (Res ords & actuation signal. y Comm. Rotms) n i d. Performance of a d. Annual d. OST 1.33.23 M' l OJt .fildgh " Purr Test". (OST 2.33.20) .$

m - ER f Hoom:,

M - Simulatoe Bldg. Rooms Out-B_Ldg h: N n

$ - Admin B dg. (Records OST 1.33.27 o Room) Q i

d O.

c O

m Q

. 0%

n.

h. ,,

Fw* Na D*M=gg War . ,

g C '4

~

O

~

o &

r o ra 4 ."r :- m y e--

O n 1 f- ~ (D

-- n

3 c c

> U

{}

SW . ,,

ime t.m w's C '

. . _ . _ . . . . _ . _ . _ _ . . . ..m __ _ . _ _ . _ , _ _ . _ . _ _ _ . _ . -_ _ _ . .

e ,

o TABLE 4 ( Page 8 of 10) z c

n SYSTEM RE(fu l REMEN I SURVEILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNI T 2) I a

l I O

! 7. F i re Ba r rie r All fire rated assemblies a. Veri fication that the a.1. 6 months .a.1. Unit if21:

l Penet ra t ions separating non-safety f i re doo rs a re $

OST 1.33.5 e related fi re areas and operable and f ree (OST 2.33.5) 5 all applic able penetration or obstructions.

• g sea t s (int luding fire a.2. Annual a.2. Out-Bldg ht doors, ri s e dampers. OST 1.33.25 etc.) asscciated with  %

n a reas protected by total m flooJing (O2 or Halon p Systems si.all be operable A.

(Units 1 4 2). $m W

E0 n

M m

n M

4 (D

• Q rJ T 00 M (J O us o (D

(D C=

O C rh

.M fD (D '

0%

er C

Dat.

Due N

K.

.t C

ren A N O y ^s% .' W

,n,

% .. E, .

W ~' fD si e- -n

(, @

S- ~- t:f c.

r RJ . ,

q

a ,

TABLE 4 ( Page 9 of 10) M C

O H

SYSTEM REQUll:EMENT SURVEILLANCE REQUIRENENI REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) $

n O

r1

3. foam System for The foam system shall be Performance of a Annual OST 1.33.11 @

the Aux. Boiler ope ra b l e. runctional test of the y fuel Oil Storage foam system and determine 8

Tank (Unit 1) satisfactory qua li ty or foam. v1 ra-rt (D

c.

B Q

W CD n

n rt W

4 n3 m

Wa N 00 U O O

v.

Q.

C O.

• S a =

w l

C w,

We e eks. -

Y$

~$.,

C7

~.

su , . ,

f!

x:  % n 59 .- y 4 A p W .. t G rf M (.;- m n n U a:., -,

c

~3%

vy

l TABLE 4 ( Page 10 of 10) f n

W SYSIEH REQUIREMENT SURVEILLANCE REQUIRENfNT REQUIRED FREQUENCY REFERENCE UNIT 1 (UNIT 2) $

M O

n

9. Fire Extinguishers l'i re ex t i ngu i st',e rs sha l l a. Verif'y each fire a. Monthly a. OST 1.33.15A. B&C (Applicable to be operat ie and in their extinguisher is @ -'

(OST 2.33.15A, B&C) t Units 1 & 2 designate $ locations. operable and in its and Out-Bldgs.) correct pnsition. 8 r.n

b. Perform maintenance b. Annual b. MSP 1.33.05

• checks on each MSP 1.33.06 m extinguisher and check (MSP 2.33.05) weight of the gas suppression-type (MSP 2.33.06) $

3 (Ha1on + CO2) firn .y ext ingui she rs. r ta rt

- P1

-W rt W

m eWk 'C n

O m n O

O "-

C h-A g.

en. .-

9 a,

o -v n H ("~ l3' g .

y C2 g see +. n W e... @

O f. r1 3 4 m c l

> W C'

~,

M'

%= - a l

,..~-

J j rem ,,

[

L Nuclear Group - Sits Administrative Procedures f-2te4,4 f:

i 41,sL.Jjl Chapter 9D 3t;kh,ECNMbbh'I'd A

liiW ne f INSTRUCTIONS UPDATED FIRE PROTECTION APPENDIX R REVIEW REPORT -'BVPS UNIT 1 FIRE PROTECTION SAFE SHUTDOWN REPORT --BVPS UNIT 2 These instructions define the methods and responsibilities for the

initiation, review, approval and distribution of changes to the BVPS Unit 1 l Updated Fire Protection Appendix R Review Report and the BVPS Unit 2 Fire l

Protection Safe Shutdown Report.

l INSTRUCTIONS i

l

1. Personnel who prepare design changes, procedures and NRC correspondence shall determine if the design changes or procedures affect the Unit' 1 ,

or Unit 2 Fire Protection Reports. All proposed-changes to the Fire i Protection Reports shall be prepared utilizing the Fire Protection Appendix R Review Report Proposed Change Form (Figure 1A).

2. Each proposed change shall be forwarded with a completed Proposed Change Form to the Nuclear Engineering Manager for processing.

3. NED shall assign a sequential reference number and shall coordinate review of each proposed change. Review responsibilities are identified in Table 1A (Unit 1) and Table 2A (Unit 2).

4. The assigned section reviewers shall perform the technical review of the proposed change (s) within the date noted on the review sheet. Any comments shall be jointly resolved and dispositioned by NED and the Licensing Section/ Fire Protection Group.

5. NED shall coordinate the review by OSC and ORC.

6. NED shall coordinate word processing, reproduction and distribution.

l i

l Page 61 of 64 Revision 4 l

l q9 ,-y,w .y- -g%+ > - * * - - - - - + - - - - - p p+,--9-- -e m-' - - -e' - 7 - - - 'T>m' -'-*eQrw ~s - y w w,

Nuc1scr Group - Site Administrativa Procsduras O Chipter; 9D

'**fE)E]u.arit!L]pL L!! ,.,3?

ATTACHMENTA(continuedh[j[j;<I ~

TABLE 1A Unit 1 Fire Protection Appendix R Review Report Sections Review Responsibilities Section Title *PRI *SEC SEC 1 INTRODUCTION MNE MNS SLS-2- HISTORICAL BACKGROUND MNS MNE- SLS 3 UNIT DESCRIPTION MNE SLS FPE 4 SHUTDOWN CAPABILITY

SUMMARY

PM MNS SLS S ELECTRICAL ANALYSIS MNE SLS FPE 6 RESOLUTION OF PROBLEM AREAS MNE SLS FPE 7 PROCEDURES (OM 56C) PM SLS FPE 8 IDENTIFICATION OF HIGH/ LOW PRESSURE MNE SLS FPE.

SYSTEM INTERFACES 9 UPDATED RESPONSE TO NRC STAFF'S MNE MNS SLS GENERIC LETFER 81-12 10 APPENDIX R REQUIREMENTS J AND 0 (RCP MNE SLS FPE OIL COLLECTION AND EMERGENCY LIGHTING) 11 EXEMPTIONS MNS SLS FPE 12 SCHEDULE FOR COMPLIANCE MNS SLS FPE

• PRI - Primary Responsibility

• SEC - Secondary Responsibility APPENDIX R REPORT REVIEWER INDEX MNS - Manager, Nuclear Safety i

j SLS - Senior Licensing Supervisor FPE - Fire Protection Engineer l

MNE - Manager, Nuclear Engineering i

PM - Plant Manager (or Asst.)

Page 62 of 64 Revision 4 I

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

3

~

• l i' 'f r4 ,rgo Chapter 9D NuclearGroup-Site'AdministrativeProcedures((351'I(Idhl![i L . y

,* 1 TABLE 2A ATTACHMERT A*(contdued) bi Unit 2 Fire Protection Safe Shutdown Report Sections Review Responsibilities.

Section Title ~*PRI *SEC -SEC 1 INTRODUCTION MNE MNS SLS 2 SYSTEMS PM MNS. S LS .

3 FIRE AREA REVIEW MNE SLS FPE.

APPENDIX Al FIRE AREA DRAWINGS HNE SLS FPE APPENDIX A2 EQUIPMENT AND COMPONENTS CONTROLLED PM MNS. SLS FROM ALTERNATE SHUTDOWN PANEL APPENDIX A3 CABLE MATRIX MNE SLS FPE APPENDIX A4 FIRE PROTECTION SAFE SHUTDOWN PM MNS SLS ANALYSIS PROCEDURE APPENDIX AS BREAKER COORDINATION STUDY MNE SLS FPE APPENDIX A6 REFERENCES MNE SLS FPE TABLE 1 FIRE HAZARDS ANALYSIS MNE SLS FPE

• PRI - Primary Responsibility

• SEC - Secondary Responsibility APPENDIX R REPORT REVIEWER INDEX MNS - Manager, Nuclear Safety SLS - Senior Licensing Supervisor FPE - Fire Protection Engineer MNE - Manager, Nuclear Engineering PM - Plant Manager (or Asst.)

Page 63 of 64 Revision 4

a U

Nuc1:er Group - Sito Administrativs Proc:dur:s j " '.# '. ;: Chrptsr 9D

JI V !i;, 3; ,

/

ATTACHMENT A (continued)

'atLi FIGURE 1A PROPOSED CHANGE FORM APPLICABLE FIRE PROTECTION REPORT (check one):

Updated Fire Protection Appendix R Review Report - BVPS Unit 1 Fire Protection Safe Shutdown Report - BVPS Unit 2 TO BE COMPLETED BY THE INITIATING GROUP:

List Page(s), Table (T), or Figure (F) numbers to be changed.

(Attach marked up pages showing proposed changes).

Reason for change:

Prepared By Date Reviewed By Date (DLC Supervision)

TO BE COMPLETED BY NED (Designated FPARRR Coordinator)

Date Received Reference No.

NED (FPARRR Coordinator or designee) Date Sent Out for Review TO BE COMPLETED BY APPENDIX R REPORT SECTION REVIEWERS:

No. Comments Comments Attached Prie:r; D::: [] []

Secondary Date Secondary Date b)

OSC Review Date Meeting No.

ORC Review Date Meeting No.

Ef fective Date of Change: Rev. No.

Page 64 of 64 Revision 4

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