ML20195E201
| ML20195E201 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/01/1988 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20195E194 | List: |
| References | |
| GL-88-12, NUDOCS 8811070290 | |
| Download: ML20195E201 (95) | |
Text
. _ _ _ _
1 ATTACHMENT
- A I
f
.1 Revise! tho' technical speci '
ions as follows:
Removs Pages Insert Paaes
'3/4 3-46 3/4 3-46' 3/4 3-47 j
3/4 3-48 4
3/4 3-48a 3/4 7-35 3/4 7-36
[
3/4 7-37 t
3/4 7-38 I
3/4 7-39 3/4 7-40 i
3/4 7-41 3/4 7-42 3/4 7-43 i
3/4 7-44 I
3/4 7-45 l
B 3/4 3-3 B 3/4 3-3
[
t B 3/4 7-7 B 3/4 7-7
[
t 6-2 6-2 t
l I
f 6-5 6-5 6-23 6-23 l
t License Condition 2.C(5)
Revised License Condition 2.C(5) t i
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TABLE 4.3-1 h
REMOTE SHUTDOWN MONITORING INSTRUMENTATION
~
SURVEILLANCE REOUIREMENTS
<>r b
k CHANNEL CHANNEL e
INSTRUMENT CHECK CALIBRATION C
- 1. Intermediate Range Nuclear Flux M
h.A.
8 s.
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.
yx OR
- 5. Reactor Coolant Temperature - Hot Leg M
R os
- 6. Reactor Ooolant Temperature - Cold Leg M
R 7.
Pressurizer Pressure M
R w-85 8.
Fressurizer Level M
R
$N
- 9. Steam Generator Pressure M
R u
j
- 10. Steam Generator Level M
R 7
- 11. RHT Temperature - HX Outlet (3)
M (S)
R
- 12. Auxiliary Feedwater Flow P_ ate S/U (2)
R Yg Notation (1) Operability required in accordance with Specification 3.3.1.1.
(2) Ct.annel 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 ensurcs that sufficient capability is available to permit shutdown and maintenance facility from locations outside of the control of HOT STANDBY of t' 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.
l 3/4.3.J.7 CHLORINE DETECTION SYSTEMS z
i The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate i
protective action in the event of an accidental chlorine release.
The chlorine det ection system will protect the control room operators j
by initiating control room isolation in a timely manner to assure the chlorine concentration in the control room does not exceed tha toxicity limit of 15 ppm by volume within 2
minutes following detection.
This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory j
Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators l
Against an Accidental Chlorine Release," February 1975.
3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION l
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters i
to monitor and assess these variables during and following an
)
accident.
This capability is consistent with the recommendations of 1
Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled l
Nuclear Plants to Assess Plant Conditions During and Following an Accident,"
December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task l
Force Status Report and Short-Term Recommendations."
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BEAVER VALLEY - UNIT 1 B 3/4 3-3 PROPOSED WORDING I
t PLANT SYSTEMS BASES 3/4.1 13 AUXILIARY RIVER WATER J,YSTEM ine 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 attucture or any other extrenely remote event would render all of the normal RIVER WATER SYSTEM supply pump 1 inoperable.
BEAVER VALLEY - UNIT 1 B 3/4 7-7 PROPOSED WORDING
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I ADMINISTRATIVE CONTRO7A t
6.2.2 UNIT sTAEF j
The unit organization shall be subject to the following:
a.
Each on duty shift chall be composed of at least the minimum a
shift crew composition shown in Table 6.2-1.
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e b.
At least one-licensed Operator shall bo in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be in the control room during reactor
- startup, scheduled reactor shutdown and 3
during recovery from reactor trips.
i d.
An individual qualified in radiation protection procedures i
shall be onsite when fuci is in the reactor.
L e.
ALL CORE ALTERATIONS after the initial fuel loading shall be f
directly supervised by either a
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during thic l
operation.
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f.
Administrative proceduros shall be developed and implemented i
to limit the working hours of unit staff who perform safety-related functions; senior reactor operators, reactor operators, radiation control technicians, auxiliary operatora, meter and control repairman, and all personnel
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actually performing vork on safety related equipment.
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j The objective shall be to have operating personnel work a normal 8-hour
- day, 40-hour week while the plant ic J
operating.
- However, in the event that unforseen problems require substantial amounto of overtimo to be used, or
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during extended periods of shutdown for refueling, major i
maintenance or major plant modifications, on a temporary l-basis, the following guidelines shall be followed:
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a.
An individual should not be permitted to work more than i
l 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> atraight, excluding shift turnover time.
b.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour
- period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
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l BEAVER VALLEY - UNIT 1 6-2 i
l PROPOSED UORDING
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ADMINISTRATIVE CONTROLS 6.3 PbCILITY STAFF OUALIFICATTQJIS, 6.3.1 Each memoor 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, Septe.nbar 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.
15 REVIEW AND AUD_II 6.5.1 ONSITE SAFETY COMMITTEE (OSql FUNCTION 6.5.1.1 The OSC shall function to advise the Plant Manager on all i
matters related to nuclear safety and shall provide review capability in the areas oft 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 l
1.
instrumentation and control l
COMPOSITIQt{
6.5.1.2 The Plant Safety Review Director is the OSC Chairman and i
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 N18.1-3971 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 chall meet the qualifications of Section 4.2.3.
l DEAVER VALLEY - UNIT 1 6-5 PROPOSED WORDINC
ADMINISTRATIVE CONTROLS a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
b.
Inoperable Seisuic 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.
Scaled source leakage i.)
excess of limits, Specification 4.7.9.1.3.
f.
Miscellaneous reporting requirements specified in the Action Statements for Radiological Effluent Technical Specifications, g.
Containment Inspection Report, Specification 4.6.1.6.2.
l h.
Steam Generator Tube Innervice Inspection Results Report, l Spocification 4.4.5.5.
6.1 RECORD RETENTION 3
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 naintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
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, i.
Records of annual physical inventory of all sealed cource material of record.
BEAVER VALLEY - UNIT 1 6-23 PROPCSED WORDING
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' Revised License Condition 2.C(5)
(5)
Zire 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 2
provision:
The Licensee may make changes to the approved fire protection program without prier 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
l Proposed Technical Specification Chango No. 138 Revision 1 Safety Analysis __
Description of amendment request:
The proposed revision provides a
complete update of our previous submittal to remove all fire protecticn related requirements from the technical specifications.
These changes reflect the guidance provided by the NRC in accordance with Generic Letter 88-12 and incorporate changes to the Administrative Centrols provided by Amendment No. 131.
The following changes are proposed:
1.
Section 3.3.3.6 (Fire Detection Instrumentation) and corresponding Bases Section 3/4.3.3.6 have been deleted, and the requirements contained therein have been 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 has been deleted to reflect the above change.
Table 3.3-10, Fire Detection Instruments, has been transferred to administrative procedures.
Item 18 of Technical Specification Table 3.3-10 will be replaced by the Primary Auxiliary Luilding (PLB) smoke detection instruments which are included in Site Administrative Procedure (SAP) 9D "Fire Protection."
Item 18 of Technical Specification Table 3.3-10, which provides the fire detection instruments for the Unit 2 control room zones 7,
8 and 9, has been included in the applicable Unit 2 section of SAP-90.
The chemical Addition Building smoke detectors will be included as Item 25 in SAP-9D.
These instruments have been added to ensure fire detection capability is available for safety related equipment located in the PAB and Chemical Addition Building.
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2.
The following plant system specifications have been deleted:
1 a) 3.7.14.1 Fire Suppression Water System, b) 3.7.14.2 Spray and/or Sprinkler Systems, 2 Systems, c) 3.7.14.3 CO i
d) 3.7.14.4 Fire Hose Stations, e) 3.7.14.5 Halon Systems, 3
f) 3.7.15 Fire Barrier Penetrations, g)
Bases 3/4.7.14 Fire Suppression Systems, l
h)
Bases 3/4.7.15 Fire Rated Assemblies, and i) 6.9.2 item g.
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bttcchm:nt B (Continued)
Proposed Technical Specification Change No. 138 Revision 1 Page 2 The requirements of these specifications have been incorporated into the UFSAR and plant procedures.
Based on the guidance provided in Generic Letter 88-12, the requirement of specification 3.7.14.1 Action b
for applicability to the provisions of specification 3.0.3 vill be incorporated into the Fire Protection Program edministrative procedures (SAP 9D).
The Fire Protection l
Program and revisions will continue to be reviewed by the Or ite Safety Committee (OSC) in accordance with specification 6.5.1.6 item a.
3.
Section 6.2.2 item f
Fire Brigade requirements and 6.4.2 Emergency Squad training have been deleted.
The requirements of these specifications have been transferred to the plant operational procedures.
4.
Specification 6.5.1.2 has been revised to correct an editorial error, the title "Composition" has been added.
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 condition le no longer necessary.
The proposed changes do not involve any physical changes to plant safety related systems, components or structures and will not change the function or operation of the Fire Protection Systems.
These changes move the requirements from the tochnical specifications to the UFSAR and SAP-9D which are identified as the Fire Protection Program.
Review of the Fire Protection Program and revisions to it will continue to be performed by the Onsite Safety Committee in accordance with specification 6.5.1.6 item a to ensure the required systems are maintained ready for uso during the required modes of plant operation.
Fire Protection Program commitments and amendments i
will be transferred from the jurisdiction of 10 CFR 50.90 (Technical Specifications) to 10 CFR 50.71(e) and 10 CFR 50.59 (UFSAR) and the reporting requirements will be addressed in accordance with 10 CFR 50.72 and 10 CFR 50.73.
The proposed changes do not involve any significant changes in requirements and are consistent with the NRC recommendations provided by the NRC in Generic Letters 86-10 and i
88-12.
Therefore, based on the
- above, these changes have been l
determined to be safe and will not reduce the margin of safety of the plant.
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1 ATTACHMENT C
l Proposed Technical Specification Change No. 138 Revision 1 No Sicnificant Hazard Evaluation Basis for proposed no significant hazards consideration determination:
The Commission has provided standards for determining whether a significant hazards consideration exists in accordance with 10 CFR 50.92(c).
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the passibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a
significant reduction in a margin of safety.
The proposed changes do not involve a
significant hazards consideration because:
1.
Section 3.3.3.6 (Fire Detection Instrumentation) and corresponding Bases Section 3/4.3.3.6 have been deleted, and the requirements contained therein have been 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 has.been deleted to reflect the above change.
Table 3.3-10, Fire Detection Instruments, has been transferred to Site Administrative i
Procedure (SAP) 9D.
It1m 18 of Technical Specification Table 3.3-10 will be replaced by the Primary Auxiliary l
Building (PAB) smoke detection instruments which are included in SAP-9D.
Item 18 of Technical Specification Table 3.3-10, which provides the fire detection instruments for the Unit 2
control room zones 7,
8 and 9, has been included in the applicable Unit 2 section of SAP-9D.
The chewical Addition Building smoke detectors will be included as Item 25 in SAP-9D.
These instruments have been added to ensure fire detection capability is available for safety related equipment located in the PAB and Chemical Addition Building.
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 fire detection instrumentation requirements from the Technical Specifications and places them into the site fire protection program and procedures and the UFSAR without altering them.
Review of the Fire Protection l
program and its revisions will continue to be the responsibility of the Onsite Safety Committee (OSC) in accordance.with specification 6.5.1.6 item a.
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AttCchm;nt C (C ntinu:d)
Proposed Technical Specification Change No. 138 Revision 1 Page 2 b)
This change does not create the possibility of a now or different kind of accident from any previously evaluated.
The proposed change does not alter the requirements; it just moves them from the Technical Specifications to the UFSAR.
Plant procedures will continue to provide the specific instructions for implementing the
- LCo, action, and surveillance requirements.
There has been no reduction in commitments
- and, as incorporated into the plant procedures, this change meets the requirements of the existing Technical Specif ications.
c)
This change does not involve a significant reduction in the margin of safety No change is being proposed to the requirements therselves.
Section 3.3.3.6 is being
- deleted, and the requirerents 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 recided 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 (c) and 10 CFR 50.59.
The reportability criteria of 10 CFh 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 requirement of specification 3.7.14.1 Action b
for applicability to the provisions of specification 3.0.3, which will be incorporated into the administrative procedures (SAP 9D) at the time of approval and issuance of this T.S.
amendment, have been transferred to the UFSAR and SAP-9D.
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.
This change removes the fire suppression water system requirements from the Technical Specifications and will place them into SAP-9D and the UFSAR without altering them.
Review "f the Fire Protection Program and its revisions will be the responsibility of the OSC, just as it has alwr.ys been the responsibility of the OSC to review changer, to fire protection requirements when they were part of the Technical Specifications.
Attcchrant C (C:ntinutd)
Proposed Technical Specification Change No. 138 Revision 1 Page 3 b)
This change does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed change does not alter the requirements; it just moves them from the Technical Specifications to the UFSAR.
Plant procedures will continue to provide the specific instructions for implementing the
- LCo, action, and surveillance requiremunts.
There has been no reduction in commitments
- and, as incorporated into the plant procedures, this change will meet the requirements of the existing Technical Specifications.
c)
This change does not involve a significant reduction in the margin of safety.
Plant procedures will continue to provide the specific instructions necessary for the implementation of the requiremento from specification 3.7.14.1.
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) and 10 CFR 50.59.
The reportability criteria of 10 CFR 50.72 and 10 CFR 50.73 are still applicable.
3.
Section 3.7.14.2 (Spray and/or Sprinkler Systems), 3.7.14.3 (C07 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 SAP-9D.
Section 6.9.2 item g
has boon 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 SAP-9D 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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Attcchment C (C:ntinu:d)
Proposed Technical Specification change No. 138 Revision 1 Page 4 b)
This change does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed change does not alter the requirements; it just moves them from the Technical Specifications to the UFSAR.
Plant procedures will continue to provide the specific instructions for implementing the
- LCO, action, and surveillance requirements.
There has been no reduction in commitments
- and, as incorporated into the plant procedures, this change meets the requirements of the existing Technical Specifications.
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
- 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) and 10 CFR 50.59.
The reportability criteria of 10 CFR 50.72 and 10 CFR 50.73 are still applicable.
4.
Section 6.2.2.f Site Fire Brigade Requirements and Section 6.4.2 have been
- deleted, and the requirements contained therein have been transferred to the plant operational procedures.
Review of the Fire Protection Program and implementing procedures and revisions thereto will continue to be the responsibility of the Onsite Safety Committee (OSC) in accordance with specification 6.5.1.6 item a.
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 site fire brigado requirements from the Technical Specifications and places them into SAP-9D 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.
Attcchnant C (Cantinutd)
Proposed Technical Specification Change No. 138 Revision 1 Page 5 b)
This enange does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed change does not alter the requirements; it just moves them from the Technical Specifications to the UFSAR.
Plant procedures will continue to provide the specific instructions for implementing the
- LCo, action, and surveillance requiremen*.s.
There has been no reduction in commitments
- and, as incorporated into the plant procedures, this change meets the requirements of the existing Techrical Specifications.
c)
This change d(es not involve a significant reduction in the margin of safety.
No change is being proposed for the requireucuts themselves.
Section 6.2.2.f and Section 6.4.2 sre being deleted, and the requirements contained therein are being incorporated into the UFSAR.
Plant procedures will continue to provide the specific instrt.ctions necessary for the implomontation of the requ',rements, just as they had when the requirements rasided in the Technical Specifications.
Fire Protect ir n Program commitments and amendments will by this process be transferred from the jurisdiction of 10 CFR 50.90 to 10 CFR 50.71(c) and 10 CFR 50.59.
The reportability criteria of 10 CFR 50.72 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 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 I
result in any loss of control of the change process.
Previously, changes to the Fire Protection Program that I
decreased the level of fire protection in the plant I
could only be made with prior Commission approval l
utilizing the license amendment process (10 CFR l
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.
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Atttchment C (ccntinued)
Proposed Technical Specification Change No. 138 Revision 1 Page 6 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 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.
Fire Protection program commitments and amendments will I
by this process be transferred from the jurisdiction of 10 CFR 50.90 to 10 CFR 50.71(e) and 10 CFR 50.59.
The l
reportability criteria of 10 CFR 50.72 and 10 C?R 50.73 are still applicable.
The proposed changes do not involve any physical change to plant safety related
- systems, components or structures, wi.11 not increase l
the likelihood of a malfunction of safety related equipment, increase the consequences of an accident previously analyzed, nor create the possibility of a
malfunction different than previously' evaluated.
t The function and operation of the Fire Protection Systems remains unchanged.
Therefore, based on the above, the changes have been determined to be safe and do not involve a significant hazards consideration.
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ATTACHMENT D
Updated Final Safety Analysis Report Section 9.10 "Fire Protection" (Changes noted by revision bar at margin) t l
BVPS-1-UPDATED FSAR rov. 5 (1/87) 9.10 FIRE PROTECTION SYSTEM g'
Based on guidance provided in Generic Letter 86-10(0, the Facility Operating Licens'e 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 Proce, dure (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 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.
9.10.1 Desian Bases The fire protection system for Beaver Valley Power Station - Unit 1 (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.(O The likelihood of a fire spreading from g
one Unit to the other is considered unlikely due to the fcilowing:
plant design features and existing fire barriers relative to fire loadings in each fire area, physical separation between BVPS-1 and BVPS-2 plant structures with the exception of shared facilities (i.e., intake strveture and control room) as defined in Section 1.7 which have been analyzed per GDC 5, and defense-in-depth criterion utilized at both BVPS-1 and BVPS-2 relative to fire prevention, detection, and suppression 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 of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a
fire emert,ency.
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9.10-1 t
6
BVPS-1-UPDATED FSAR rov. 5 (1/87)
The system is designed in accordance with the standards of the National Fire Protection Association and is generally based on the r
recommendations of the insurance underwriter (American Nuclear
(
Insurers).
The fire protection system is designed on the basis that rupture or inadvertent operation will not significantly impair the cafety capability of structures, systems, or components important to cafety or designed to seismic Class I requirements.
Fire Protaction(0, requires that each 10 CFR 50 Part 50.48 operating nuclear power plant have a
fire protection plan that catisfies GDC 3
of Appendix A.
The plan, described in SAP 9D Fire Protection, identifies the overall fire protection
- program, the crganization and responsibilities for the program, and outlines the plan for fire protection for the site.
The plan also describes cpecific features necessary to implement the program and the means to limit fire damage to structures, systems and components important to cafety so that the capability to safaly shutdown the plant is ensured.
Certain fire protection features that have been accepted by the NRC to catisfy the provisions of Appendix A to Branch Technical PoJition 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 June 6, 1979.(**d Clarification and guidance with respect to permissible alternatives to catisfy Appendix A to BTP APCSD 9.5-1 is provided in the NRC document
/
Nuclear Plant Fire Protection Functional Responsibilities, 5
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 I
in the DLC Quality Assurance Program Appendix C - Fire Protectiert.
l Appendix R
to 10 CFR Part 50(O establishes fire protection features required to sat!'.y GDC 3 with respect to certain generic issues for BVPS-1 (licensed to operate prior to January 1, 1979),
cpplicable only as per the following:
-Section III.G:
Safe Shutdown capability
-Section III.J:
-Section III.0:
RCP Oil Collection System 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 creas of.the plant were granted per NRC letters dated March 14, 1983, l
August 30, 1984 and December 4, 1986.
9.10.2 Description The fire protectior. systems are shown schematically in Figures 9.10-1 I
and 9.10-2.
Design data for major components of the fire protection k
system are given in Table 9.10-1.
9.10-2 j
l
BVPS-1-UPDATED FSAR R0v. 5 (1/87) diesel generator cubicles following a
CIB signal and undervoltage
(
condition on the emergency busses.
Release of CO2 during operation of the diesel generator could result in stalling the diesel generator engine by the displacement of combustion air with CO.
When CO2 2
is discharged in an emergency diesel generator cubicle, safe plant 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 cccurrences.
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.
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.
2.
Tests on water spray systems serving outdoor facilities include the discharge of water and the observance of spray patterns, t
3.
Yearly waterflow tests are made to verify that the normal water supply is available and to indicate the possible presence of closed valves.
4.
A semi-annual inspection (Spring and Fall) will be conducted of exterior hydrants to ensure that hydrant barrels are dry and the threads are lubricated.
An annual operational hydrostatic test of hydrcnts will be performed to verify barrel integrity following l the winter freeze (O.
9.10-11 i
I
BVPS-1-UPDATED FSAR RGv. 5 (1/87) 9.10.5 Fire' Protection Bases 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 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 integral element in the overall facility fire protection program.
In tho 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.
9.10.5.2 Fire Suppression Systems The operability of the fire suppression systems ensures that adaquate fire suppression capability is available to confine and extir.guish fires occurring in any portion of the facility where safety-related equipment is located.
The fire suppression system consists of the water
- system, spray and/or sprinklers, CO,
Halon and fire hose 2
stations.
The collective capability of the fire suppression systems is adequate to minimize potential damage to safety-related eculpment and is a major element in the facility fire protection program.
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 fighting than if the inoperable equipment is the primary means of fire suppression.
The test requirements identified in Site Administrative Procedure 90 provide assurance that the minimum operability requirements of the 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 systems are
- 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 system becomes inoperable, corrective measures must be taken as defined in the administrative procedures since this system provides the major fire suppression capability of the plant.
9.10-13
BVPS-1-UPDATED FSAR R0v. 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 cperability.
9.10-14
i BVPS-1-UPDATED FSAR RGv. $ (1/87) h References for Section 9.10 4
(
- 1. Appendix A
to Branch Technical Position APCSB 9.5-1, Guidelines '
l 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.
I 3, 10 CFR 50.48 - Fire Protection for Operating Nuclear Power Plants.
l i
1
- 4. Amendment No.
18 to the Beaver Valley Power Station Unit No. 1, l
Operating License DPR-66.
l
- 5. Appendix R to 10 CFR 50.
l f
i
i
- 7. Updated Fire Protection Appendix R Review Report for BVPS Unit 1.
i 8-Letter from S.
A.
- Varga, Chief Operating Reactors Branch #1, I
Division of Licensing, NRC to J. J. Carey Vice President, Nuclear i
- Group, DLC, dated May 14, 1985.
Subject:
"Clarification of f
l Amendment 18, Fire Hydrant Barrel Inspection Frequency".
- 9. NUREG-1057 Safety Evaluation Report Related to the operation of j
(
Beaver Valley Power Station, Unit l
i l
l 1
I i
i f
l
[
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I l
9.10-15 l
1 i
ATTACHMENT E
Site Administrative Procedure 9-D "Fire Protection Program" l
I
_l
+l j
c DUQUESNE LIGHT COMPANY Nuclear Group j
Site Administrative Procedures Chapter 9D FIRE PROTECTION l
Chapter Index Page 1
I.
PURPOSE 1
II.
APPLICABILITY 1
III.
DEFINITIONS IV.
ORGANIZATION AND RESPONSIBILITIES 2
7 V.
REFERENCES 8
VI.
INSTRUCTIONS 8
A.
Requirem.nts 9
B.
Operation 10 C.
Maintenance 10 D.
Inspection and Testing E.
Control of Ignition Sources 10 F.
Control of Combustibles and Flammable Liquids 11
(,
G.
Engineering Design and Procurement Document Control 12 13 H.
Training 15 1.
Prefire Plans 15 J.
Quality Assurance 15 K.
Physical Requirements 15 L.
Program Review 16 H.
Records N.
Out-of-Service Requirements /Reportability 16 Figure 1 - Administrative Organizational Chart 18 Figure 2 - Site Fire Brigade Organizational Chart 19 l
Figure 3 - Fire Protection Impairment / System 0.0.S. Form 20 Table 1
- Operability Requirements for Fire 21 Protection System Table 1.1 - Fire Detection Instruments - Unit 1 26 Table 1.2 Fire Detection Instruments - Unit 2 2S Table 2
- Fire Protection System Surveillance 35 Requirements Table 3
- Fire Insuranco ( ANI) Operability Requirements for Fire Protection System 46 Table 4
- Fire Insurance, (ANI) Surveillance Requirements for Fire Protection 56 System
(
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.,.x DUQUESNE LIGHT COMPAh7 Nuclear
- Group Site Administrative Procedures Chapter 9D i
1 FIRE PROTECTION l
Chapter Index Page Attachment A - Instructions, Updated Fire Protection Appendix R Review Report - BVPS Unit 1 and Fire Protection Safe Shutdown 66 Report - BVPS Unit 2 Table 1A - (Attachment A) Unit 1 Fire Protection App. R Review Report Section Review Respcasibilities 67 Table 2A - (Attachment A) Unit 2 Fire Protection Safe Shutdown Report Sections Review 68 Responsibilities Figure 1A - (Attachment A) Proposed 69 Change Form i
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DUQUESNE 11GET COMPANY Nuclear Group Site Administrative Procedures
'(-
Chapter 9D FIRE PROTECTION 1.
PURPOSE To define the administrative authorities, responsibilities and requirements of the Site Fire Protection Program.
APPLICA BILITY Applies to all Nuclear Group personnel. The basic fire protection administrative organiza', ion chart is shown on Figure 1.
DEFINITIONS NOTE:
Certain words (such as OPERABII, 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 Arts is the portion of a building or plant that is separated it.or other areas by boundary fire barriers (walls, floors, and ceilings including seals, fire dampers and
- ~
doors).
those conponents of construction (walls, B.
Fire Barriers are floors. ceilings) that ire rated in hours of fire resistance to prevent the spread of fire.
C.
Sub areas or 7enes are subdivisions of fire areas in which to combat particular fire suppression systems are d.esigned types of fires.
D.
A Fire Vatch or Fire Be.jyict Attendant is an individual assigned to attend open fire barriers (fire
- door, penetration.
etc.),
to monitor areas during periods when existing fire protection systems are inoperable, or to monitor work processes 6e! equipment or room conditions t'or possible fire hazards. The individual shall be trained in fire reporting procedures and portable fire extinguishing equipment.
E.
Innitson _ Source is any form of welding, soldering, brazing, grinding or open flame imrk.
F.
Combustible Material is any material that will burn or sustain the combustion process whether or not it exhibits flame under exposed fire cos.dttions.
k Page 1 ef 69 Revision 5
i Nuclear Group - Site Administrative Procedures Chapter 9D G.
Fire Re ta rdant Vood is treated wood which exhibits ilte retardant properties or wood coated with a U.L.
listed fire
(
retardant compound having a flamo spread er '.t 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.
R.
Incipient-type Fire is a fire in its initial or beginning stage that can be controlled or extinguished by portable extinguishing equipment.
IV.
ORGANIZ ATION AND RESP 0NSIBILITIES An Administrativ. Organization Chart, Figure 1 depicts the organization relative to +he implementation of the fire protection program.
(.
A.
Supervisory personnel shall have the authority and responsibility for activities which ae conducted by individuals under their general supervision with respect to the fire protection program.
B.
Department Ma.. agers have responsibility for the activities conducted under their control. They, in turn, are to hold accountablo each supervisor, staff member and worker for ths proper performance of activities associated with the fire protection program.
C.
The Manager.
Quality Assurance Unit is responsible for developing and implementing an inspection and audit program that verifies DLC compliance with the Fire Protection r
Program.
D.
The Manager, Nuclear Engineering Department is responsible for ensuring that plant modifications comply with design criteria for fire protection, and has respotsibility for evaluating update requests and maintenance of the BVPS Unit 1 Updated Fire Protection Appendix R Review Ryort (UFPARR9) 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 k
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Nuclear Group - Site Administrative Procedures Chapter 9D and processing of proposed changes as per the instructions
,(,
provided in Attachment A of this procedure.
\\
l E.
Section reviewers identified in Tables 1A and 2A of Attachment A are responsible for review of proposed chans,es to the BVPS Unit 1 UFPARR nd the 1".T; 'Jnit 2 FPSSR.
l F.
The Manager, Nuclear Safety has responsibility for the overall administration of the fire protection program.
l G.
The Manager, Nuclear Training is responsible for development, impletrontation and revision of the fire training program, as well as coordinating, scheduling and providing classroom training.
'l H.
The Director of Licensing is responsible for directing the efforts atsociated with the implementation of the fire protection program.
l I.
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 anc performing the two-year review per SAP 11.
l J.
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 Brigado 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 f.
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 aff'e. ting fire protection and prevention.
6.
Responsible for evaluating and analyzing fire hazards and activities concerning fire protection and prevention.
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Nuclear Group - Site' Administrative Procedures W ""! M e.* MSM Chapter 9D 1
7.
Provide the Nuclear Group staff with technical information and expertise,' as required, in the area of
(
fire orotection and prevention.
(.
8.
Responsible for processing of open burning permit for purpeses of fire school trainia; en en enual 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 Fi*gure 2 -
Sit'e Fire Brigadu (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 Brigado of at least 5 members shall be caintained on site et all tices.
The Fire Brigade shall not include 3 members of thr minimum shift crew necessary for safe shutdown of the unit or cny personnel required for other essential functions durics; a Id re emergency. 8 Hembers of the Site Fire Brigade are assigned responsibility as follows:
1.
Brigade Chief - Nucicar Station Operating Foreman (or,
(
in his absence, as assigned by on-duty Shift Supervisor).
c Coordinates activities between Brigade & Control Room in the execution of ener3ency procedures.
b.
Determines what actions are necessary to control and extinguish the fire as well as evaluating radiological hazards.
c.
Ensures that the nccessary fire suppression systs.ms are activated and that the Fire Brigade members safety utilize the proper equfpment.
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.
e.
Determines if an area should be evacuated of non-essential personnel and the ' escape route (s) that should be utilized.
kl Page 4 of 69 Revision 5 1
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I Nuclear Group - Site Administrative Pro'cedures oy, r,
, Chapter 9D.,
..,[h}
c 6
2.
Brigade Captain - Nuclear Control Operator (or, in his absence, as assigned by on-duty Shift Suoervisor)
(~
Assumes duties of the Chief in his absence.
1 a.
b, Directs the fire-fig. ting operations of the
- brigade, c.
Clears all energized equipment (without affecting safe shutdown capability) which may endanger safe exocotion of fire fighting activities of the Brigade personnel.
d.
Assures availability of necessary emergency equipment.
3.
Additioaal Brigade members:
The additional Brigade members carry out the orders a.
of the Brigade Captain in controlling and extinguishing the fire and/or caring t'o r 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 ala r; and respond properly and in accordance with 9pproved pre-fire plan procedures / strategies.
3)
To use available rescue and ' ire-fighting 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.
6)
To cooperate with offsite fire department personnel in a coordinated fire-fighting effort.
4.
Firo_Sarshall(s) - A fire marshall may be.iny one of the foll owing:
- Any qualified brigade member
- Any DLC supervisor, qualified as such through the fire training program Page 5 of 69 Revision 5
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Nuclear Group - Site Administrative Procedures Chapter 9D
'll a.
Shall be qualified to handle incipient-type fires in accordance with fire training progrnm.
b.
Shall aid in safely evacuating non-essential personnel from the area.
t.
c.
Shall assist the brigade so as to alleviate and minimize the consequences of the fire emergency.
1; 5.
Brigade Assis: ant (sj ; The Brigade Chief is authorized to r
commandeer any qualified DLC employee to assist the Brigade force when such assistance is required.
It is the responsibility of those commandeered DLC employees s
to perform the assigned tasks to the best of their ability without disruption to the Brigade force.
b e
C I'
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4 rage 6 ef se nevisien 5
Chapter 9D Nuclear Group - Site Administrative Procedures V.
REFERENCES 1.
BVPS Unit 1 (2) FSAR, Section 9.10 (9.5.1 and Appendix 9.5A) f
- Fire Protection System (FPS).
2.
BVPS Unit 1 (2) Technical Specifications.
3.
BVPS Unit 1 (2) Operating Manual, Chapter 33 (2.33), FPS.
4.
BVPS Unit 1 (2) Operating Hanual, 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, Chspter 56C (2.56C)
Alternate Safe Shutdown ftom Out ide Contxo1 Room.
7.
BVPS Units 1/2 Maintenance Manual, Secti
'3 General Work Practice Procedures.
S.
Fire Protection Safety Evaluat ion Report dated May 3,1979 issued by the NRC for BVPE 1 o'ech. Spec., Amendment 18).
9.
Appendix A
to Branch Technical Position APCSB 9.5-1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976.
10.
Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assuranc.e, NRC letter dated August 29 1977.
1 1'.
10 CFR 50.48 - Fire Prot. for Operating Nuclear Power Plant.
12.
Appendix R to 10 CFR 50.
13.
14.
Updated Fire Protection App. R Review Report for BVPS 1.
l 15.
Fire Protection Safe Shutdown Report for BVPS Unit 2.
16.
NRC Inspection Reports 87-11 and 87-17 for BVPS Unit 2.
17.
Appendix C of DLC - Operations QA Program.
18.
Safety Evaluation Report (SER) related to BVPS No. 2 (FJREG 1057), Section 9.5.1 Fire Protection Program.
1 Facility Operating License No. NPF-64, BVPS Unit 2.
19.
i 20.
QA Audit Response (BV-C-87-12), ND3VPN:5307 dated Jan. 29, 1988.
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Nuclear Group - Site Administrative Procedures Chapter 9D-i i
VI, INSTRUCTIONS
.(i A.
Requirements 1.
All a-tivities 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.
"Fire Protection," requires each 3.
10 CFR 50.48 opcrating 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 permissibic 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 p
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.
4 l
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Chapter 9D Nuclear Group t Site A'dministrative Procedures Exemptions for specific fire areas of the plant were
['.
granted per NRC letters dated March 14, 1983; August 30,
\\
1984; December 4, 1986; and July 27, 1987.
W 6.
Branch Technical Position (BTP) CMEB 9.5-1, which is part of the acceptance criteria vi Standard Ravic.: Plar 9.5.1 (NURE.G 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 Eranch Technical Pc,sition (BTP)
CHEB 9.5-1.
BVPS Unit 2 utilites 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 SAP to 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 portabic fire protection equipment shall be operated in accordance with Operating Manual Chapter Firo Protection System, and Operating 1.33 (2.33)
Hanual Chapter 1.55A (2.55A) - Operations Surveillance Testing of Fire Protection Equipment.
3.
Permanent and portabl.e fire protection equipment should not be used for purposes other than fire protection.
l Page 9 of 69 Revision 5 l
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N Cha}4er 9D' O-Nuclear Croiip "Siti Adaninistrative Procedures ~-
C.
Maintenance
- r g
1.
Maintenance or repair of fire protection systems, equipment or elements shall be requested and performed in, accordance with SAP 3D, "The M.tintenance Work Request." The Fire Protection Engineer shall review maintenance work requests tracking reports for MVRs categorized as Category "F" or classified as Operating Manual System Chapter 33, "Fire Protection System". "
2.
First-linn supervisors shall ensure the requirem*ents for transient combustibles, ignition sources, and fire barrier penetrations or barriers are met as described in 3
Maintenance Manual Section 13.
D.
Inspection end TestinJ 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 f.-
procedures.
(
4.
Operations testing for fire protection related equipment (33 series) is performed in accordance with Operations Surveillance Tests (OSTs).
5.
Maintenance testing for fire protection related equipment (33 series) is performed in accordance with Maintenance Surveillance Procedures (MSPs), Preventive Maintenance Procedures (PHPs), Corrective Maintenance Procedures (CMPs) and Instrument Calibration Procedures (ICPs).
6.
Post-maintenance te.ing shall, be performed in accordance with SAP 8A, "Maintenance," and SAP 3D, "The l
[
Maintenance Work Request."
{
7.
Operations Quality Control (0QC) activities that govern i,
surveillance and inspection of maintenance for fire protection related equipment (Category F) are identified in OQC Procedures.
E.
Control of Ignition Sources 1.
Any activity involving an ignition source (such as welding, cutting, grinding and open flame work)
Page 10 of 69 Revision 5
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1-Chapter 9D m w.. W A.
Nuclear Group ' Site Administrative Procedures ~
r' potentially affecting safety related equipment shall be l
i governed by a Hot Work Permit in accordance with the
~.
BVPS 1/2 Maintenance Manual, Section 13.
The Area Work Permit (SAP 41) is an acceptable alternative to.the use llot Work Pezmit during maintenance outage periods of a and for work activities in non-safety related areas b
(yard creas, fab shops, etc.)'.
t 'gd 2.
Smoking is pr hibited except in designate.d areas of the plant. Smoking areas have been specifically designated and identified with signs posted in areas.
F.
Control of Combustibles and Flammable LiquJds 1.
Control of transient combustibles' and flamnable liquids shall be in accordance with Operating Manual 1.56B.4 1
-(2.56B.4),
"Fire Prevention and Control,"
and-Maintenance Manual, Section 13.
Procedures have been developed to establish the following controls:
a.
All waste, r%bris, scrap, rags, oil spills,'or other unneccessary combustibles resulting from work activity in safety-related areas are to be renoved and/or cleaned up as soon as possible.
1)
For noncontinuous work activities, highly combustible materials will be cleaned up at
(..
the end of the shift or activity, whichever is sooner.
2)
Low hazard combustible material will be removed at the end of the work ectivity.
b.
Approved trash containers are provided in safety-related areas.
c.
Periodic inspections for accumulation of combustibles and transient fire loading during maintenance are conducted in safety-telated areas in accordance with housekeeping procedures.
d.
Combustibles required for operation and maintenance in safety-related areas are stored in proper receptacles or approved storage cabinets.
Stairwells are not used for storage of combustibles.
Flammable liquids required for mai 2 mance are issued only in fixed amounts and in approved containers.
e.
Charcoal and particulate filters not stored in approved fire-retardant containers will be removed from safety-related areas as soon as possible or k
Page 11 of 69 Revision 5
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1 Chapter 9D stored in areas serviced by a deluge spray or sprinklet system.
'( 'I a
f.
Transient combustible materials in-safety-related-
~
areas will not be left unattended unless special provisions have bean provided or the material is properiy stored. The Fire Protection Engineer will be - contact ed, if necessary, to specify additional fire ' protection for potential transient fire hazards that cannot be avoided.
i*
- g..
The primary fire protection concept for the Reactor Containment area is to minimize the use of combustible materials.
During maintenanco and outage periods, administrative controls will be adhered for controlling transient fire loads.
h.
The combustibio contents
.et the Condensate Polishing Building vill be confined to the specific
-areas protected by automatic sprinkler systems.
The ventilation system charcoal filter provided with a heat detuctor with control. room alar.e indication and manual deluge system capability is an exception.2 1.
All luraber and wood required for use will be treated. Fire-retardant wood will be ' limited to (o
teoporary use.
Large wooden timbers, or any s
special size or application-type lumber not available as treated wood, may be coated or wrcpped with an Underwriters' Laboratory (UL) listed fire-retardant compound or material.
Exceptions are wood in the form of crates or shipping boxes (including any packing material) which will be removed as soon as possible after removal of equipment from boxes.
In addition, wooden step ladders and relay test rigs required for certain job functions are acceptable p.uvided they are stored properly after use.
s G.
Engineering Design and Procurement Docu' ment Control 1.
Except for certain Fire Protection System (FPS) valves that interface with Category I Systems, fire protection equipment shall be designated as "Category F".
The special category designation is to insuce that the guidelines for
- design, procurement, installatior.,
testing and inspection and administrative controls for the fire protection system are adequately reviwed and controlled. CW rations Quality Control (0QC) activities associated with these requirements are described in applicable OQC procedures, Page 12 of 69 Revision 5 i
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Nuclear Group:- Site Administrative Pro'cedures-Chapter 9D s
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2.
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 applicable NFPA Standards.
l 3.
Preparation, review and approval of procurement and design documents tha11 be accomplished in accordance with written procedures. The Fire Protection Engineer shall be includet in the review cycle and shall review and approve all purchase requisitions and design documents assoclated with fire protection equipment regardless of cacegory.
4.
Modifications to the Fire Protection System shall be designed utilizing the guidelines of NFPA Codes and with consideration of recommendations from the Fire Insurance carrier. The following documents shall be considered in the design of physical modifications to permanent fire protection equipment, BVPS Unit l'- Updated Final Safety Analysis Report q-(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).
5.
Any changes involving fire protection equipment and/cr systems shall be reviewed for compliance wich applicable l
NFPA codes.
l 6.
Prior to installation of new equipment or major modification to existing equipment, design drawings of FPS and equipment installations shall be submitted to the Fire Protection Engineer and the fire insurance carrier for review and approval.
7.
The Fire' Protection Engineer shall perform in-process inspections of FPS new installations or modifications to i
the FPS.
8.
The.BVPS Unit 1 UFPARRR and the BVPS Unit 2 FPSSR shall be periodically updated. Changes to the Reports shall be made per Instructions provided in Attachment A to this SAP.
Page 13 of 69 Revision 5 y
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Chapter 9D Nuclear-Gro'up. Site-Administrative Procedures H.
Training 1.
I'nstruction
/
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),
NFPA 27-1976, and the guidelines established in BTP CHEB 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 trainfag 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.
Classrocm instructions, with training aids such as literature and other audio and/or visual aids, and practical, hands-on tr ining are provided to familiarize the members of the Fire Brigade in fire fighting techniques and equipment.
c.
Fire Watches and Fire Barrier Attendants are l
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.
j d.
Fire Marshalls are given periodic training in fire-fighting and evacuation procedures and escape routes, as t.ppropriate, Training records shall be maintained for at least 3 e.
years.
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 protec;; ion and/or first aid equipment.
L Page 14 of 69 Revision 5 i
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.Nuc ear Groupi-Sits Administrative Procedures s 3;, m f,' Chapter.s9D..
a 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 useassent of equipment and Brigade effectiveness.
d.
All fire brigade personnel will participate in a-retraining program over e two (2) year period.
A site fire drill will be conducted with local fire e.
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 riot procedures or instructions per se, but serve as are resource information to be used for training purposes and by the fire brigsde as an aid to fire fighting.
J.
Quality Assurance 1.
Fire Protection shall be conducted in accordance with Operations Quality Assurance Appendix C _of the DLC 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 acco: dance with guidelines of ANSI N-546 conducted every three years, and an annual review by the Duquesne Light Company Medical Department to screen personnel for medical problems.
Revision 5 Page 15 of 69
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,s-Nuclear Group - Sife Administrative' Procedures 4 Chapter'9D';
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' L.
Program Review 1.
Audits shall be conducted utilizing the guidelines of
' " N.
Generic Letter 82-21 and performed under the cognizance of the Of fsite Review Committee. "
a.
The f2re 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 ptevention program inspection and audit shall be performed at least once per 12 months utilizing either qwalified offsite licensee personnel, an outside fire protection firm, QA or American Nuclear Insurers (ANI).
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.
2.
The fire insurance carrier periodically performs independent inspections and audits of the fire protection and prevention program. Resolution of items or recommendations from audits and inspections shall be handled in accordance with NGD 8 "Audits and Inspections".
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.
Oat-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.
a.
The Fire Protection Impairment / System OOS Form (Figure 3) should be initiated by the work party and verified by Operations.
~
l b.
Refer to Tables 1 and 3 of this SAP for required actions to be taken for fire protection equipment inoperability.
If a fire watch is required, the Fire Watch Log (OM 54, Log L8-2) shall be utilized.
Page 16 of 68 Revision 5
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Jm Nuclear Group --Site Administrative Pro'cedures -
Chapter 9D 2.,
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I 2.
An inoper'able or partia11'y inope'rab1A 'li.e., degraded) fire protection system or component as defined in Table 1 and-Table 3 of this SAP shall be evaluated and considered for reporting as an impairment per SAP 3B, "Reporting Requirements", and appropriate actions taken.
Reportability criteria of 10 CFR 50.72 and 10 CFR. 50.73 l
should be evaluated for applicability.
a.
Notifications of impairments shall be made per SAP 3B, as appropriate.
b.
For applicability to 10 CFR 50.73, consideration for a fire event should be postulated when evaluating the degraded or inoperable condition for its potential effect on safe shutdown capability
(
Reference:
SAP 13. "Preparation of Draft Incident Reports, Unit Off Normal Reports and Conduct of Critiques".).
Revision 5 Page 17 of 69
I
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NUCLEAR CROUP - SITE ADMINISTRATIVE PROCEDURES CHAPTER'9DT p
FIRE PROTECTON' '
ADMINISTRATIVE ORGANIZATIONAL CHART NUCLEAR GROUP-pdCLEAR GROUP VICE PRESIDENT GENERAL MANAGER GENER AL MANAGER CORPORATE
' NUCLEAR OPERATIONS NUCLEAR SERVICES NUCLEAR NUCLEAR ENO4NEERING MANAGEMENT PLANT SERVICES DEPARTMENT ~--
SAFETY TRAINING
=--
^^
MANAGER MANAGER MANAGER MANAGER DIRECTOR LICENSING l
SENIOR LICEN11NG SUPERVISOR FIRE PROTECTION ENGINEERS LEGEN0 COMMAND COMMUN4CATKW k
FIGURE 1 Page 18 of 69 Revision 5
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CHAPTER 9D
. l NUCLEAR GROUP - SITE ADMINISTRATIVE PROCEDURES E
_,f_'
' fs) e's s
, L SITE FIRE ERKRADE (EMERGENCY SQUAD) ORGANIZATIONAL CHART FIRE BRIGADE CellEF NUCLEAR STATION OPERATING FOREMAN U
FRE BRIGADE CAPTAIN NUCLEAR CONTROL OPERATOR Y
AiXHT10NAL BRIGADE MEMBERS GAINMUM OF THREE (3) TOTAL)
QUAUFIED BRIGADE MEMBERS U
FIRE MARSHALLS
- OUAUF1ED BRIGADE MEMBERIGJ
- QUAUF1ED DLC SUPERVISOR (S) u BRIGADE ASSISTANTS
- COMMANOEERED EMPLOYEE (S)
FIGURE 2
(
Page 19 of 69 Revision 5
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MUNO.rd..fO['d Nuclear Group - Site Administrative Procedures Chapter 9D y
FIRE PROTECTION IMPAIRMENT / SYSTEM 0.0.S./ FORM Date:
Time:
Check one: Unit 1 [ ]/ Unit 2 [ ]
(
Clearance Permit No.:
(Attach to Clearance Permit, if applicable)
- 1. Affected System: CO: [ ],
Halon [ ],
Water [ ]
(Check one)
O t
- 2. Building / Area affected:
- 3. Date/ Time - 0.0.S.
/
/
- 4. Expected Return to Service Date:
- 5. Reason for' System 0.0.S. (Failure, MVR, PHP, OST, BVT, etc.):
- 6. SAP 9D Table 1 or 3 Requirements:
- 7. Valve (s) Closed:
(I.D.)
- 8. Panel De-energized:
(I.D.)
- 9. Name of Work Group Supervisor:
- 10. Fire Watch Provided: YES [ ],
NO [ ]
(Check one)
- 11. If #10 was checked YES, type of fire watch?
Continuous [ ],
Hourly [ ]
(Check one)
I NOTE:
dTILIZE FIRE WATCH LOG, OM 54, LOG L8-2.
- 12. Was F.P. Engineer notified? YES [ ),
NO [ ]
(Check one)
I i
NO [ ]
(Check one) i t
By Whom:
- 14. Compensatory Measures taken? YES [ ],
NO [ ],(Check one)
- 15. If 014 was checked YES, then identify the compensatory measures:
(
i
- 16. Signature of NSS authorizing the work:
/
i NSS Date f
FORWARD COMPLETED COPY TO F. P. ENGINEER. ATTACH ORIGINAL TO CTIARANCE PERMIT OR NVR.
e 1
r FIGURE 3 I
Page 20 of 69 Revision 5 f
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TABLE 1 (P;931 cf 5)
UPERASILITY REQUIREMENTS FOR FIRE PROTECTION SYSTEM NOTE:
Prior to removal or any major portion or the FPS or upon discovery that a major piece or FPS equipment or section is out-of-service. the fire insurance carrier ( ANI) shall be notified (Refer to SAP 38).
CAUTION: EXCEEDf8dC OPERA 81LITV REQUIREMENTS CONSTITUTES A REPORTABLE OCCURANCE (Refer to SAP 13 guidelines and SAP 38, as O".
applicable).
O D to 'cn SYSTEM REQUIREMENT APPLICA8t.E HODES CONDITION REQUIRED ACTION TIME REQUIREMENT g$
tw -
P*
>+ 1 1 Fire Detection Instrumentation for whenever the equip.
- a. With the number a.1. Outside cnet.
Nm Instrumentation each fire zone that is being of OPERABLE rire a) establish an a) Within I hr.
r protecting safety-p rotected is detection hourly fire E
related equipment required to be instruments less watch patrol g-shall be OPERABLE.
than required by in the C:
Table 1.1 affected g
IJo l t 1:
(BVPS #1) or a rea.
W D
kefer to Table Table 1.2 r'
1.1 of this SAP (BVPS #2) s.2. Inside cnet.
s e
l " "E a) inspect a) Within 8 arrected hrs.
oo Unit 2:
cnet. zone n,
O Refer to Table every 8 hrs.
, y:
1.2 of this SAP 93
~e
(
w b) monitor cnet.
b) Within 1 hr.
4 -
air temp.
-, 7
.o j every hr.
m
. tn ' rs '
- b. Restore to
- b. Within its days.
. Ef e
OPERABLE status 1 c fy Q
> a 2.
Fire Suppression
- s. Two OPERABLE fire At all times, a.1. One pump a.1. Restore to a.1. Within 7 days.
- tW Water System suppresion pumps inope rabl e.
OPERABLE status
$ q..
I I
aligned to the gg h,w,
fire suppression p Nvide an t" y -
.-% gwj header.
al ternate pump.
.?O j ?p.1 a.2. Two pumps a.2. Provide a a.*!. Within 21. hrs, Inope rab le.
backup fire a
suppression
. " %..I water system.
?a{
o <
- h. Operable flow At all times.
M. Flow path
.$. Provide a backup.h. Within 2ta hrs.
- w " a T,o {;.
path (Applicable I nope ra b l e.
fire suppression i
to Units 1 & 2).
water system.
5 mf 1
.gg a
X n.
..t
=
'w' 2,A pe b.ind AcN., ut sahis,dd,;, th speci2 :;;e te h-ut se a.,
Me :
kopera 48le him pa A, app /y the apan es & Te c%/ Speckinka 3.o.1
TABLE * (Page 2 Cf 5)
Price to removal af sny majsr portion of the FPS or upon discovery that a moJEr pieco cf FPS equipment er section GS out-
'g P6OTE:
c of-service, the fire insurance carrier ( ANI) shall be notified (Refer to SAP 38).
~ n-e' CAUTION: EXCEEDieIG OPERA 88tfTY RECulREMENTS COMSTITUTES 'A REPCMTA8t E OCCURAI!LE (Refer to SAP 13 guidelines and SAP 38, as ~
appaacable).
i
. c3 SYSTEM REQUIREMENT APPLICABLE MODES C0000lilO81 REQUIRED ACTIO*l TIME REQUIREMElli g
c:
'O '
?. (continued)
- c. The SVPS #2 At all times.
- c. Booster Pump
- c. Restore to
- c. Within 7 days.
Sooster Puso inope rable.
OPERABLE status o
m ao., p.
- (capacity 623 9pe) g capable to taking provide an alternate water.
e Suction free the Service Water Cys supply to the fire suppression E$
(SWS) & aligned to the Unit 2 water sys capable N3 hose rack stations of supplying
$y backup water to u-r for the sarety e
related equipment the applicable safety related
_.Q a rea s.
equipment a reas.
.N. re c:, a
- 3. Spray and/or The following whenever the equip.
- a. One or more or
- 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 />.
- e.
r, Sprinkler System sprinkler systems bei protected is the selected hourly fire watch
.g.
so serving areas shall requ red to be portions patrol in the og m O O
be OPER/ ALE:
Inoperable in affected area areas containing with backup fire ad a w
redundant systems supp ression O
O.
N Applicable to h.g, $,
Units 1 and 2:
or components.
capability.
- Cnet. ( RHR Area )*
(See flOTES Below) e O
- >*mt m
- Cnet. (Cable Pen.
- 8
- b. Restore to
- b. Within las days.
7.g Area)*
OPERABLE status.
m.. s.
- Aux. FW Pump Area **
,,s
- CCR Pump Area g'
- Main Filter Bank
- Cent. todine d
Cha rcoa l Filters DA (BV-2) r*
s.
- PA8 735, 752 and T.'
768 ieveIs (BV-1)
^
ac s
e.
es
- e u
o W
- p60T C-With Cnet. area Sprinkler System inoperable, check this area during scheduled cnet. entries in Modes 1-ta and once per m o g7-shift in Modes 5 and 6.
v o-
- such time as the backup Aui. FW Pump i s ope ra b l e ( BV-1 ). establish a continuous fire watch whenever Unit l's g
r S
"peOTE:
Until Aux. FW Pump Sprinkler System is inoperable.
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TABLE 1 (r:ge 3 er 5) 2C Prior to removal of any major portion of the FPS or upon discovery that a major piece of FPS equipment or section is out -
O-SeOTE:
shall be notified (Refer to SAP 38).
g or-service, the fire insurance carrier ( ANI) e
~#
CAUTIOM: EXCEEDillC OPERABILITY PECUIREMENTS COPIST I TUT ES A REPORTABLE OCCUR _AMCE - (Refer to SAP 13 guidelines and SAP 38, ' as spp6& cable).
On' SYSTEM REQUIRE > TENT APPLICABLE MODES CONDITION REQUIRCO AcilON TIME REQUIREMElef h.
~
Is CO2 System The following CO2 whenever the equip.
CO2 System
- a. Establish a
- s. Within I hour.
lo 9
M' Systems shall be being protected is inoperable for any continuous fire OPERABLE:
required to be of the a reas.
watch in the OPERADLE.
arrected ares (s)
Unit 1 Areas:
NOTE:
with backup rire g y
- Cable f ray Unit 1:
supp ression t'
o-g N
Mezzanine System OPERABLE with capability.
M :s >
- Cable Vaults min. level or 30%
- Diesel Generator
& min. pressure or
- b. Restore to
- b. Within its days m.
W I
E. "g
- 275 psig in OPERABLE status.
Rooms associated storage c 2 Unit 2 Areas-tank.
" '"ri
- Cable Spree :ng 44 Area Catri. Bldg.
Unit 2:
- t
- Instrumentation System OPERABLE with l:g g-2 Room Cntrl. Bldg.
min. lesel or 81%
el - n
- Communication Room
& min. pressure Gr
.M Q
oo 295 psig in the two W
Cntri. 85dg.
'y'e,
- Cable Tunces 10 ton storage u ' O= -
u tanks (TK-22&23).
- $i W
Between CntrI. k Aux. Bldgs.
The backup storage
- M ;e ;
o
- Cable Tunnel Aux.
tank (TK-216) shall m
have min. level or
., p* :
8tdg.
- Cable Vault & Rod 70% and min.
' C'8 0 q) pr-2ssure or Cntrl. Areas, f
- Cable Spreading 295 psig.
-g Area Service Bldg.
y
- Emergency Diesel Generator Bldg.
p Room
- tg ;'
.w p.
oo -
e w
"p.
p
~,
obt m<n
- 3"I b
30 On
-D o
V OL 1' Mj e
2GF Q
- n Mo
- s cP
' 7^
- 3rT;l4 f{
w
,y%I
- c..
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- ?.!,
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T ABLE 1 ( P r, > 0 c r 51 n out-
- E Prirr t3 removal cr tny majgr portion of the FPS cr upon disc %very that a maj%r Glec3 cf rPS Lquipment Cr tection of-service, the fire insurance carrier ( ANI) shall be notified (Refer to SAP 38).
FOTE:
w CAL *T I CN: EXCEEDING OPERABILITY R EQUI REMENTSJQNST I TUTES A REPORTABLE OCCURANCE (Refer to SAP 13 guidelines and SAP 38 as *g applicable).
o Sf$iLM REQOIREMENT APPLICASLE MODES CONDilaON REQUIRED ACTION TIME REQUlRLMENT o
4
- 5. Fire Hose Hos-stations Whenever the equip.
One or more selected
- a. Provide equivalent a. Within 1 hr. ( ts 1.>
Sta tions serving the in the areas stations inoperable.
capacity backup hours for cnet.
O, m
following areas protected by the hose protection area hose r
shall be OPERADLE:
selected stations is to the unprotected stations) ir o
a rea.
the inoperable required to be
- ( See NOTES Below) station is the ls >
Unit 1 Areas:
primary means t*
c.
- Prima ry Aux. Bldg.*
of fire y&
- ruel Bldg.'
protection in the 4c
- Intake Structure
- arrected f.rea; y
- Service Bldg.
otherwise, withir n
(Safety-Related 2ts hrs.
- N A rea s ) *
(See NOTES below) l$"
y
- Safeguards Bldg.
ps: r
( Pipe Tunnel
- b. Restore to
- b. Within 14 days.
4" A rea s )
- OPERABLE Status.
- Containment **
8
~3 Unit 2 Areas:
n 00
- fuel k Decon Bldg.*
.T m
- Diesel Generator M
Bldgs.
n
'.'l- ",
- Cable Vault Areas m
& Relay Room o
o"
- Service Bldg.*
- Aux. Bldg.'
W
- Containment **
e
- Cntri. Bldg. &
I Cable Tunnel y
- Sa regua rds',
b I
- 5. Halon Systems Halon Systems Whenever the equip.
- a. One or more of a.
Establish a
- a. Wi thin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
E'-
protecting the being protected is the selected continuous fire rollowing areas required to be systems watch in the
~
sharl t be OPERABLE.
inoperable in arrected area m -. "
- d areas containing with backup fire redundant systems supp ression n"o Unit 1 A reaJ:
o
- Process Equipment or comoonents.
capability.
3 Area (Zone 1)
- b. Restore to
- b. Within 114 days.
- Process Equipment OPERABLE status.
C' Area (Zone 2) i" h
- Cable Tunnel (CV-3) y
~
Exceptions would be aress or
.S.
Denotes areas or badgs. where primary means or fire protection is fire hose racks.
et portions covered by auto suppression systems (i.e., Cable Vault areas, DG Bldgs., certain areas of the PAB, etc. ).
S CNOTE:
e o
entries in Modes 1-te and once por es 3
With Cnet. area Hose Stations inoperable, check this area during scheduled Cnet,
"* NOTE:
p shift in Modes 5 and 6.
t C
S
+.=
.s iae
- a_
y
h.
A O
TABLE 1 (Pige $ cf $)
Prior to remoral of any major portion of the FPS or upon discovery that a major piece of FPS equipment or section is out-NOTE:
o-of-service, the fire insurance carrier ( ANI) shall be notified (Refer to SAP 38).
w CAUTICN: DtCEEDING OPERABittTY REQUIREMENTS CONSTITUTES A REPORTABLE OCCURANCE - (Refer to SAP 13 guidelines and SAP 38, as
$'4 M
apptscable).
o n;
0 SYSIC.M REQUIREMENT APPLlCABLE MODES CONDITION REQUIRED ACTION TIME REQUIREMENI
.o 8
o':.
e
- 5. (continued)
Unit 2 Aren:
.o en
- Cntrl. 81dg.
- Cntri. Bldg.
Computer Room West Com. Room N.>
ta n.
H e.
T.
fire Barrier All fire rated At all times One or more
- a. 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 />.
H W d
Penet ra tions assemblies (wall s, inoperabl e, continuous fire
(
watch on one side se e.
f Icor/cei l ings, of the affected g g rus cable tray enclosures ba rrie r c:.p<
a nd othe r fi re ba rrie rs ) sepa ra ting QR H rt :
- b. Verify the
- b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
% 7' safety related fi re OPERA 818.lTY of
,e a rea s o r sepa ra t G.)g fire detectors on at least one side 7
97 portions of M
redundant systems of the inoperable to o; Important to safe Q.
o shutdown within a barrier y
A o : o.'
E y
fi re a rea a nd a l l u
establish an 38 C; sealing devices in hourly fire watch 2;
fire rated assembly e:
penetrations (fire pa t ro l.
' *t8 doors, fire windows,
- c. Restore to
- c. Within 7 days.
cn fire dampers, cable OPERABLE status.
and piping penetration seals ar ventilation seats)
- NOTE:
shall be OPERABtC Degredation of fire H
4 wrap or fire proof h
(Units 1 and 2).
material will t*
tus 3 require:
- NOTE:
r Fire wrap for cable and duct work, and
- 1) Eng inee ring evaluation 7
fire proof material QS m
t coating of
- 2) Establish fire 80 a t ructu ra l steel
.sould be included watch per above In the above defined required actions.
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Nuclear Group - Site Administrative Procedures
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Chapter 9D
,' I TABLE 1.1 t.
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:
i instrument 1,ocation Minimum Instruments Operable Smoke
.:aat
-1. Control Room
- Control Room Area 4
N/A 1
- Computer Room
- Vertical Board 2
4*
' 2. Cable Spreading Hezzanino
- East Zone 10
- Vest Zone 10
- 3. Vest Cable Vault 3
3*.
I l
- 4. East Cable Vault 3
3*
- 5. Normal Switchgear Room N/A i
f' East Zone -
4 West Zone 4
?
- 6. A/E Emergency Switchgear Room 3
N/A
- 7. D/F Emergency Switchgear Room 3
N/A
- 8. Remote Shutdown Panel Process Instrument Room 8
N/A Underfloor Area (hV Area)
(See NOTE 1 below)***
Underfloor Area (SW Area)
(See NOTE 1 below)***
j
- 9. Station Battery Rooms (each)
N/A 1/ Room l
- 10. Relay Room 1
N/A I
- 11. No,'1 Diesei Generator 2
1*
l
- 12. No. 2 Diesel Generator 2
1*
L
- 13. Upper Charcoal Filters N/A 6**
NOTE 1:
Zones are associated with a Halon-protected space. Each space has f
two separate detection circuits (zones).
One zone, in its f
entirety, needs to remain operable.
{
Page 26 of 69 Revision 5
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Chapter 9D 259 san '
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Nuclear Grou'p-- Site' Administrative Procedures 5
TABLE 1.1 (continued)
Instrument Location Minimum Instruments Operable
~
Smoke Heat
- 14. Lower Charcoal Tilters N/A 6**
- 15. Control Room Air Conditioning Room 2
N/A
- 16. Reactor Trip Breaker Room 3
N/A 17 Primary Auxiliary Bldg. (PAB):
PAB Elev. 735' 5
7**
l PAB Elev. 752' 8
N/A PAB Elev. 768' 7
N/A
~
- 18. Charging Pump Cubicle 1/ cubicle N/A 4
N/A
- 19. Cable Vault 3 (Elev. 720' on side of
.3***
Unit 2 Control Room)
- 20. Intake Structure (A, B and C Cubicle) 6/ cubicle N/A D Cubicle N/A 1
4 4**
l
- 21. CCR Pump Area l
4 4**
- 22. Auxiliary Teedwater Pump Area
- 23. Cable Penetration Area (Cnmt)#
2/ Pen. Area 4**
l
- 24. RHR Pump Area (Cnmt)#
2/ Pump Area 4**
l
- 25. Chemical Addition Building 3
N/A 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
(#) The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment l
1 leakage rate tests.
k-l Page 27 of 69 Revision 5 l
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i Nuclear Group - Site' Administrative Procedures
- Chapter 9D
..A i
.s l.
TABLE 1.2 e.
J FIRE DETECTION INSTRUMENTS - UNIT 2 e
2-l l
As a minimum, the fire detection instrumentation for each fire detection zone shown in the Table below shall be OPERABLE:
1 Inftrument Location Minimum Instruments Operable Smoke Flanie Heat
- 1. Fire Area CB-1; Control Bldg. 707'
- Zone.11 (Comm., Inst. and Relay 11 (See NOTE 2 Below) l Room Under Floor Areas)
- Zone 2-1 Inst./ Relay Room 13*
Zone 10 (Inst. and Relay Room) 7 (See NOTE 2 Below)
- Zone 12 (HCC Room) 1 (See NOTE 2 Below) 2.' Fire Area CB-2; Cable Spreading 725'
- Zone 23 (Cable Spreading Area) 12 (See NOTE 2 Below)
- Zone 2-1 Cable Spreading Area 9*
- 3. Fire Area CB-3; Control Room
- Zone 17 (Control Roem) 8
- Zone 67 (Vertical Board) 2
- 4. Fire Area CB-4; Computer Room
- Zone,18 (Computer Room) 1 (See NOTE 2 Below)
- Zone 210 (Computer Room) 1***
$. Fire Area CB-5; HVAC Equip.
Fan Room 735'6" Zone 19 (HVAC Equip. Fan Room) 2 Zono 20 Fan Room (Duct Mounted) 1 (See NOTE 1 Below)
- Filter 2HVC*FLTA252A (2HVC-FD252A1) 1
- }11ter 2HVC*FLTA252B (2HVC-FD252B1) 1 NOTE 1:
If duct mounted detector is out of service, verify Fan Room (Zone 19) detectors are operable.
NOTE 2:
If the early-warning smoke detectors are 00S for a fire area provided with a backup smoke detection circuit (associated HALON protected areas), verify the backup with the CO2 or alarm system for the affected area is OPERABLE.
Page 28 of 69 Revision 5
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Chapter 9D I.
Nuclear Group - Site Administrative Procedures TA3LE 1.2 (continued)
' Instrument Location Minimum Instruments Operable Smoke Flame Heat
- 6. Fire Area CB-6; West Comm. Room 707'
- Zone 14 (West Comm. Room -
1 (See NOTE 2 Below) l Ceiling Area)
- Zone 310 (West Comm.
5***
l Room - Ceiling and Unt e Floor Areas)
- 7. Fire Area CT-1; Cable Tun i 712'6"
- Zone 16 (Ceble Tunnel North) 4 (See NOTE 2 Below)
- Zone 15 (Cont. Bldg./ Cable 2 (See NOTE 2 Below)
Tunnel South)
- Zone 22 (Cable Tunnel South) 4 (See NOTE 2 Below)
- Zone 36 (East End of Cable Tunnel) 1 (See NOTE 2 Pelow)
- Zone 2-1 Cabin Tunnel 712'6" 14*
- 8. Fire Area CV-1; Cab 10 Vault (West) 735'
- Zone 50 (Cable Tunnel / Aux. Bldg.)
3 (See NOTE 2 Below)
- Zone 2-2 (Cable Tunnel /
7*
Aux. Bldg.)
(.
- Zone 30 (Cable Vault West) 7 (See NOTE 2 Below)
- Zone 2-2 (Cable Vault West) 9*
- 9. Fire Area CV 2; Cable Vault (East) 735'
- Zono 31 (Cable Vault East) 5 (See NOTE 2 Below) 4
- Zone 2-2A (Cable Vault East) 4*
l
- 10. Fire Area CV-3; Cable Vault 755'
- Zone 32 (Cable Vault) 11 (See NOTE 2 Below)
- Zone 2-3 (Cable Vault) 13*
- Zone 52 (Cable Tunnel / Aux. Bldg.,
4 (See NOTE 2 Below) including ASP)
- Zone 2-3 Cable Tunnel /
6* '
l I
Aux. Bldg.
NOTE 2 if the early-warning smoke detectors are 00S for a fire area provided with a backup smoke detection circuit (associated HALON protected areas), verify the backup with the CO2 or alarm system for the affected area is OPERABLE.
(
Page 29 of 69 Revision 5
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,J-
.j Nuclear Group - Site Administrative Procedures Chapter 9D I
TABLE 1.2 (contin ad)
Instrument Location Minimum Instruments Operable i
Smoke Flame Heat
- 11. Fire Area CV-4; Cable Vault Fan Room 773'
- Zone 43 (Emer. Switchgear HVAC) 2
- 12. Fire Area CV-5; Personnel Hatch 773'
- Zone 41 (Hatch Area) 1
- Zone 42 (Purge Duct Work Are t) 2
- 13. Fire Area CV-6; Relay Roorr 755'
. Zone 53 (Relay Room) 2 (See NOTE 2 Below)
- Zone 2-7 (Relaf Room) 2*
- 14. Fire Area DG 1; Diesel Bldg. No. 1
- Zone 63 (Orange Diesel) 2 4*
- Zone 2-5 (Orange Diesel)
- 15. Fire Ares DG-2; Diesel Bldg. No. 2
(.
- Zone 62 (furple Diesel) 2 4*
- Zone 2-6 (Purple Diesel)
- 16. Fire Ar,ea FB-1; 1.el/Decon. Bldg.
- Zone 66 (Fuel Pool Cooling 1
Pumps 739)
- Filter 2HVQ FLTA227 (2HVQ-FD227) 1**(L)
- 17. Fire Area !!S-1; !!ain Steam Valve Area
- Zone 44 Cable Vault Elev. 773'6" 3
- Zone 45 Fan Room 773'6" 1
- Zone 46 Compressor Room 773'6" 1
NOTE 2:
If the early-warning smoke detectors are 00S for a fire area provided with a backup smoke detection circuit (associated HALOS protected areas), verify the backup with the CO2 or alarm system for the affected area is OPERABLE.
Page 30 of 69 Revision 5 l
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- < Chapter 9D Nuclear Group - Site: Administrative Procedures v i, i
TABLE 1,2 (continued) k' Instrument Iocation Minimum Instruments Operable'
{
Smoke F1_ame Heat
- 18. Fire Ar 1 PA-3; Aux. Bldg.
r
- Zone 49A (CCP Heat Exchanger 9
Area 710')
3*
- CCP Area (2FPw' FD270A thru F)
- Zone 49B (Aux. Bldg. 738'6")
7
- Zone 51A (Aux. Bldg. 735'6")
11 i
- Zone 51B (Aux. Bldg. Charging 7
? Pump Area)
\\
- 19. Fire Area PA 4; Aux. Bldg. 755'6"
- Zone 54A (Aux. Bldg. 75S'6" North) 9
- Zone $4B (Aux. Bldg. 755'6" South) 11
- Zone 56 (Aux. 31dg. 755'6" Duct 2 (See NOTE 1A Below)
Hounted) t
- 20. Fire Arec PA-5; Aut. Bldg. 773'6" 7
Zone 57A Aux. Bldg. 773'6" 6
North (includes Fan Room)
. (,
Zone 57B Aux. D1dg. 773'6" South 11 Zone SC (Duct Mounted) 1 (See NOTE IB Below) l 1**(L) l Filter 2HVS*FLTA205A (2dVS-FD205A) 1**(L)
Filter 2HVS*FLTA205B (2HYS FD205B) 1**(L)
Filter 2HVS*FLTA208A (2HVS-FD208A)
Filt'er 2HVS*FLTA208B (2HYS-FD208B)
.1**(L)
~
- 21. :7 ire Areas PA-6 and 7; Aux. Bldg. 755'6" i
1 Zone 55 (HCC Rooms E03 and E04) 1/ Room
- 22. Fire Area PT-1; Pipe Tunnel 716' 6" 1
- Zone 40 (Pipe Tunnel Cable Vault) 10
- 23. Fire Area SB-1; Service Bldg. -
[
Emergency Svitchgear 730'6" t
- Zone 01 (Or.ange Switchgear) 12 NOTE 1A:
If duct mounted detectors are out of service, verify the Aux.
l Bldg. 755'6" detector zones (54A and 54B) are operable.
NOTE IB:
If duct mounted detectors are out of service, verify the Aux.
Bldg. 773'6" detector zones (57A and 57B) are operable.
k Page 31 of 69 Revisien 5
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.g Nuclear Group - Site Administrative Procedures Chapter 9D TABLE 1.2 (continued)
Instrument Location (Qnimum Instruments 0 parable Smoke Flame Heat
- 24. Fire Area SB-2; Service Bldg.
Emergency Switchgear 730'6"
- Zone 02 (Purple Switchgear) 11
- 25. Fire Area SB 3; Service Bldg.
Caisle Tray 745'6"
- Zone 4A (Northern 2 Rows) 12 (See NOTE 2 Delow)
- Zone 4B (Southern 2 Rows) 12 (See NOTE 2 Below)
- Zone 2-4 Cable Ttay 13*
Area 745'6"
- 26. Fire Area SB-4; Service Bldg.
Normal Switchgear 760'6"
- Zone SA (Normal Switchgear, North) 10
- Zone 5B (Normal Switchgear, South) 7
- 27. Fire Area SB-5; Service Bldg. 780'6"
- Zone 7A (West End) 8
- Zone 7B (East End) 7
- Filter 2GSS-FLTA255A (2GSS-FD255A) 1**(L)
- Filter 2GSS-FLTA255B (2GSS-FD25!B) 1**(L)
- 28. Fire Ar'ea SB-6,7,8,9; Battery Rooms 730'6"
- Zone 03 (Safety Related Battery 1/ Room Roomm 2-1, 2-2, 2-3, 2-4)
- 29. Fire Area SB-10; Battery Room 760'6"
- Zone 6 Battery Room 2-5 1
NOTE 2:
If the early warning sanke detoctors are 00S for a fire area provided with a backup smoke detcetion circuit (associated HALON protected areas), verify the backup with the CO2 or alarm system for the affected area is OPERABLE.
k.
Page 32 of 6S Revision 5
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~
Chapter 9D Nuclear Group - Site Administrative Proceduros TABLE 1,2 (continued)
(
Minimum Instruments Operable Instrument Location Smoke Flame Heat
- 30. Fire Area RC-1; Reactor Containment (#)
- Zone 64 (Cable PeuotratJon Area) 10 2**
- Cable Pen. - Purple (21 N-FD232 A/C) 2**
- Cable Pen. - Orange (2FN -FD233B/D)
- Zone 65 (RHR Pump Area) 1 1**
- 2RHS*P21A (2FN-FD231A/B) 1**
- 2RHS*P21B (2FW-FD230A/8) 1**(L)
- Filtor 21iVR*FLTA211A (2HVR-FD211A) 1**(L)
- Filte: 2HVE*FLTA211B (2HVR-FD2118)
- 31. Fire A.ea SG IN; North Safeguards. Area
- Zone 26 (F.levation 718'6")
4
- Zone 28 (Eletration 737'6" 3 (See NOTE 1 Below) and Duct Mounted) 1**
- Aux. W Pump (23B) Area (2FN-FD234A/B)
- 32. Fire Area SG-1S; South Safeguards Area
- Zone 27 (Elevation 718'6")
4
(-
- Zone 29 (Elevation 737'6" 3 (See NOTE 1 Below) and Duct Mounted) 1**
- Aux. W Pump (23A) Aree (2FN-FD235A/B) 1**
- Steam Driven Auy.. W Pump (22)
Area (2F W FD236A/B) out of service, verify the NOTE 1:
1.
duct mounted detectors are
.wsticable Safeguard <. Area detectors are operable.
k Page 33 of 69 Revision 5
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Nuclear Group - Site Administrative Procedures-Chapter 9D
)
- f..;
TABLE 1.2 (continued)
Instrument Location Minimun Instruments Operable Smoke Flame Heat
- 33. Miscellaneous Areas:
- Zone 59 (Aux. Bldg. - Elev. Mach. Rm.)
1
- Zone 8 (Service Bldg. Stairwell) 3
- Zor.s 24 (Cont. Bldg. NorthStairwell) 1
- Zone 25 (Cont. Bldg. SouthStairwell) 1
- Zone 33 (Aux. Bldg. Personnel Passage) 3
- Zone 34 (Cable Vault Personnel Pa sage) 3
- Zone 35 (Turb. Bldg. Personnel Passage) 3
- Zone 37 (Aux. Bldg. NW Stairs) 1 (CL. 712'6")
- Zone 38 (Cont. Bldg. Personnel 2
Passage 722'6")
- Zone 39 (Control RoomEntrance Way) 3 Zone 60 (Aux. Bldg. Personnel Passage) 1 Zone 47 (Cable Vault East Stairs) 1 Zone 48 (Cable Vault Vest Stairs) 1 Table Notations
- Detectors associated with the CO system actuation circuitry.
[
- Catectors associated with the water suppression system actuation circuitry.
- Detectors associated with the Halon system actuation circuitry.
(L) Line-type (thermistor cable) heat detector.
(0) The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
Page 34 of 69 Revision 5
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TABLE 2 ( Page 1 cr 11)
- c. 4
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- - ::N t flRE PFOTECTION SYSTrM SURVEILLA80CE REQUIPEMENTS NOTE:
Each surveillance requirement shall be performed within the specirled time interval as defined in the Technical
, 7'.r
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s y; Speclrications (Section 8.0.2).
ng:
4 Failure to perform a surveillance requirement. constitutes failure to meet OPERABillTY requirements.
g ;.
J-CAUTION:
-)
i st-od.
I SYSTCH REQutREMENT SURVCILLANCC REQU1R[HCN!
R[QLilRLD TRLQUCNCY R[l[RENCL UNIT I (UNIT 2)
I f
- 1. s 2..
au em.
'48 m.
1 Fire Detection instrumentation for erch a.1.
Each or the fire n.1 6 months
- a. OST 1.33.13A Instrumentation fire zone protecting detection instrants.
OST l.33.138 g7 safety-related equipment wisich a rt accessible OST 1.33.16 a
shall be OPERADLE.
du ritu plant (OST 2.33.33A) operation shall be (OST 2.33.138)
'c* g ',
(fnft_1:
demor strated (OST 2.33.16) ps > -
gf Refer to Table 1.1 or operable by g,77 this SAP.
performing a CHANNEL t* a -
FUNCT IONAL 'T.ST.
Unit 28 Refer to Table 1.2 or a.2. Fire detectors which m.2. During each COLD An 6 M:
this SAP.
are not accessible SHUTDOWN exceeding M
.g during plant 2ra hrs unless e /..
A D
operation shall be performed in demonstrated OPERABLE previous 6 months.
$F 90 c ox.
by performing a rA tas CHANNEL FUNCTIONAL
' *y?
TEST.
c o
- b. The NFPA Stancard 72D
- b. 6 months
- b. OST 1.33.13A gg OST 1.33.138 e.w e
C* ass A supervised OST 1.33.16
- d e
circuits supervision 9
associated with the (OST 2.3?.3A) g?
detector alarms of (OST 2.33.13A) o each of the fire (OST 2.33.138)
- E ' q*i detection instrument.s (OST 2.33.16) u-shall be demonstrated g,4 OPERADLE.
n r*"
- c. The non-supervised
- c. Monthly
- c. OST 1.33.1A circuits between the (OST 2.33.3)
.S, C me local panels and the g
{r.
Control Room shall be demonstrated OPERABLE.
O
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,. g Sy$!EM REQUIREMENT SURVEILLANCE REQUIREMENT REQUIRED FREQUENCY REFERENCC'UNil 1 (UNIT 2) we a: y
" rt
- 2. Fire Suppression
- s. The fire suppression a.1 Starting each pump a.1. Weekly
- a.1. OST 1.33.7 Water System system shall be and operate on OST 1.33.8
- UQ to-j demonstra ted recirc riov for at mp OPERABLE.
least 15 minutes
-i BASIS).
" Uls, (STACCERED TEST r
.e l **4 l
a.2. Verificati~on that a.2. Monthly a.2. OST 1.33.1A lg'N
- e each valve t-Janual, (OST 2.33.1) power operated or suto) in the riow g
- 08 path is in its A h.k s
i correct pos. son.
} g ~ 7,,
33 -
i m.3. Performa ee or a s.3. Annual a.3, OST 1.33.4 E
sys yao loop and OST 1.33.6 hyd ra".t riusti.
(OST 2.33.fs)
{ -g-z - re a.ts. C.veling or each a.ts. Annual s.4. OST 1.33.12 og the riow path.
. g '. om 9
testable valve in (OST 2.33.12) j n
O 4
a.5. Performanco of a a.5. 18 months a.5. OST 1/2.33.12 e '. 2 s,
cm system runctional OST 1.33.12 t ra test which includes (OST 2.33.12) 28 simulated automatic TI om actuation of the f es system throughout fe its operating gen,
sequence, and:
4 al VeriryIng that H,'
each automatic
~
valve in the TIow r* i path actuates to 14 Its Correct 49 a-
- position, c'
n
] V, 5
b) Verifying that so each pump develops at least 2500 gpa at a system head w<
or 250 reet,
%n p.s$
w 4
D*
=O '. '
gn
.e
!e W
8
-I y3-w "NOTE:
Tested weekly per UFOAR (Section 9.10.8 )
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SYSIfM REQUIREMENT
%RVEiLLANCE REQdlREMENT REQUIRED TREQUENCY RE'EREseCE UNIT 1 (UNIT 2) p 4
e.
ft'
'M
- 2. (continued) c) CycIlng each
~go valve in the flow
>et path that.ls not O-
- 4 testable during plant operation through at least
-I-one complete cycle or frli
., en
- 6 trave t, ant.
Q:
on a S d) Verifying that y:
each high pressure
,, ; g '
pump starts c _; 3,,
38 m.
(sequentially)*to
%e 8, maintain the rire e
suppression water system pressure M
greater than or h"$
z a equal to 90 psig.
o e on M
a.6. Performance or a n.6. AnnumI*
s.6. OST 1/2.33.12 e
28 -
riow test of the E w
o system (in accordance co W
with MrPA Handbook, d'"
15th Edition, Section 16. Chap. 8) k tc which includes the Q
entire fire loop e >
(Units 1 and 2).
tn -
b, The diesel fire b.1. Verification of the b.1 Monthly b.1. OST 1.33.8
's.
pump sheiI be fuei olI day tank i
demonstrated l e' 11 (greater than
$ d' OPERABLE.
or equal to 350 ga s lons), & starting
' g '6 of the rire pump diesel engine and
.w A _;
x operating for at Q 7e[c, [
least 20 minutes.
3 7*:, >
b.2. Verirlestion that a b 2. Quarterly 0.2. CHM CP 2 ( ruel j a.,
1 Oil Specs.)
rw n
'o, {g.
sample or diesel W
ruel from the fuel CHM CP 3 FP CHM CP 8 TP-3 ola day tank is within acceptable en ; O.. j.
s.
i.
po limits (Table 1 of 7,(i !l M
ASTM D975-74) when
%7'9sf':
checked for
=;7 -
a vi scosi ty, va te r,
( e.g. } ^
s y
and sediment.
u yb:
g hih-d ;
w-r v._ ! >
"NOTE:
riow tested annual,1y per UFSAR (Section 9.10.4).
1 w.;
I Y N.. ;.
,w
^
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e TABLE 2 ( P;ge O cf" 11) 2C SyS1f M ELQuektMEN!
SURV[l LLANCE It:f20 8 RLMLNI ItiOUIRLD litlOULNGY R[f[RENCC UNil I (UNil 2) e*
am-
- 2. (continued) b.3.
Inspection of the b.3.
18 months b.3. MSP 33.01 fire pump diesel MSP 33.02 O
q engine in accordance oc with manufacturer's c
recommendations.
y, -
b.4. Verification that b.h.
18 months b.4. OST 1/2.33.12 M
the diesel starts on
.o rre auto and operates for at least 20 f9 mintues.
tn ' y L3.
c, The diesel fire pump c.1. Verirication of the c.1, Weekly c.1. OST 1.33.8
%. 33 starting 24 volt electrolyte level of
< :s D2 ' >
battery bank and each battery & the ove ra l l battery y%
charger shall be i
demonstrated OPLRAftli.'
voltage for each pn fire pump diesel g - 88 starting 24 volt
- n. p p2 4 battery brnk.
D N*
M*
c.2. Verification that c.2. Quarterly c.2. NSP 33.04 D:. o,
'8 the specific gravity C $.
w CD is appropriate for o
continued service of O
O=.
the battery.
et '
c.3.
Inspection of' the c.3.
18 months c.3. MSP 33.03 Z'O j.
batteries, to verify that:
I a) The batteries, g
cell plates &
g battery racks show no visuaI es indication of M
~
physical damage or abnormal a
deteri3 ration, &
]l -
,a b) The battery-to-battery & terminal p
connections are O
clean, tight, f ree of* corrosion
"'n f
>. er
& coated with anti-co rros ion g
Og
<g
- material, n.7 r
. 0%
ty Pt s 0
Us 07"
~ -,
.g E
~T
-mMar*
a e
,Q. '
D
^,a, $.y ju.
c
..%'s..
l ',
TABLE 2 (Page 5 or 11) tysTLM REQUIREMfMI SO R ILLAfeCE RLQUlREMLMI RtOU.fiED IREQutleCY REfLRLleCE UNil n (U8IIT 2) l t6:^#
[
l*. (continued)
- d. The fivPS #2 tiooster d.1. Starting the Booster d.1. Monthly d.4.
(OST 2.33,7)
'c.
eg Pump (capacity 623 farmp and operate O.
gpm) capable or taking for at least 1$ min.
,'~ j -
suction from the Service Wter Sys.
d.2. Verification that d.2. Monthly d.2. (OST 2.33.')
4,8:
(SWS) ar a34gned to each vaive (mantesI, the Unit 2 slose rack power operated or
'W W
stations for the a tsto ) in the flow g
sarety related pa tt. Is in its correct position.
eqisi pment a rea s.
d.3. Performance or a d.i. Annsial d.3. (OSr 2.33.a )
3 s
iB k system ritish (in g 33 '
conjurttion wiLtz the Unit i system ripsh).
. U r,e l
d.as. Cycl ing of each.
d.as. Annesa l d.4. (OST 2.33.12)
[Q I
r,.,
testable valve in g{
the riow path.
O d.$. Performance or a d.5. 18 months d.5. (OST 2.33.12A) g'W system ronctional o
test which incitedes:
b'*
ed
[ '
ts a) Verifying that
-g, the booster pump
'M i
develops at least
$.' I b8 62$ gpa at a sys.
.. en hem.i or 250 feet.
,I* g j
.4 O
b) Cycting each
. el;.. v,f e
valve in the flow g t ?"
e path that is not testable during
. te ',(
e l
plant operation through at least one complete
^
..g cycle or futi e,
travel, and
- TK c) Vererying that the booster pump maintains the fire k '"
suppression water system pressure greater than or
.O equal to 90 psig.*
l (See NOTE Defow)
[?
y 3
N l
E:
90 psig at discharge or Booster Pump and, per NFPA requirerents, 6$ psig at highest standpipe hose rack.
j
.":, n "NOTE:
m 8
,,; -, ? (2, ;
w
.-r g.
. ?t ".
- v. 1
--.n__
TABLE 2 (Page 6 ef 11)
Et Sv5TLM REQUlHLMLMI SURVEILLANCE REQUIREP.LIli REQUIRLD FRLQULNCY RC6 (RENCE UNI T 1 (UNii 2)
J
~~
w ;
g
- 2. (cor.tinued)
- e.
Fire Hydrants shall
- e,1. Hydro test each
- e.1.
Annual "e.1. OST 1.33.4 be OPERABLE.
hydrant to verify (OST 2.33.4) 0,
. ba rre l Integ ri ty ac rollowing winter
-v 9
freeze.
'4.
- e.2.
Inspection or each
- e.2. 6 months
'e.2. OST 1.33.4 hydrant to ensure (spring and fall)
(OST 2.33.4)
.g r
. n hyd rant ba rre l s a re dry and threads are f#
lubricated.
tn
- f. Hose Cabinets and
- f.1 Inspection of each
- f.1 6 months
'f.1. OST U33.5
%r Cart Houses hose cabinet & cart (OST 2.33.5)
==
u.
te r house located 8
within the perimeter M
of the plant 8
protected area to verary adequate r
7 inventory.
te g g
w 03
[ Q ~.g W
s-
- 1. Spray anet/or The following areas
- n. Verification that each
- a. Monthly
- a. OST 1.33.1A lQ *y O
Sprinkler System applicable to Units 1 & 2 valve (manual, power (OST 2.33.1) g-o
=.e shall be OPERABLE:
operated cr auto) in o
- Comt. (RHR Area) the flow path is in n
- Cnet. (Cable Pen. Area )
i ts correct posi tion.
j l 8
- Aux. FW Pump Areas
- CCR Pump Areas
- b. Cycling of each
- b. Annual
- b. OST 1.33.6 Im:* '
- Main Filter Banks testable valve in the OST 1.33.12
~
g
- Cnet. Bodine flow path.
OST 1.33.138
) 'l '
i Cha rcoa l Filters (BV-2)
(OST 2.33.6)
. = ' 'd
- PA5 735, 752 and (OST 2.33.12) g5 768 levels (BV-1)
(OST 2.33.138) 1
. h'&
c.1. Performance or a c.1 18 months c.1 OST 1.33.12 1
=.
system functional OST 1.33.13D l Y
'f, test which includes OST 1.33.21
^a simulated automatic (OST 2.33.12)
- "O 7; ectuation of' the (OST 2.33.13D) 7.-
et system, and:
(OST 2.33.21)
,m O
a ) Ve ri fying tha t
.0 the automatic o
valves in the
...wi 3dy flow path actuate O.{g. -
to their correct O
positions on a
, 's r
manual test o
signal, and n
.e D
W "Ref:
T.S. Amendment No. 18 (Fire Protection SER; dated June 6, 1979) n d
=
~ ^
65-'N*__
d
^
r a
M e
TABLE 2 (Page 7 of 11)
.n
'I SYSTEM REQUtREMENT SURVEILLANCE REQUIREMENT REQUIRED fREQUEfeCY REFERENCE UNil 1 (U8tlT 2) e e",
O' M
s 3 (continued)
,b] Cycling each valve en the flow l
g path that is not l
testable during 4-]-
]
plant operation
.ig.
e' r
through at least
- W one complete es e cycle or full
- -e travel.
l N,
am c.2.
Inspection of the c.2. 18 months c.2. OST 1.33.13D l g 'g.-
OST 1.33.21 j
dry pipe spray and l4 g'
j sprinkler headers (OST 2.33.13D) tus ea to verify Integrity.
(OST 2.33.21) y e.
l n
i c.3. Inspection or each c.3. 18 months c.3. OST 1.33.13D o"
i OST 1.33.23 n,;
nozzle's spray area I
to verify the spray (OST 2.33.13D) gis <..*
pattern is not (OST 2.33.21) 38 s
obstructed.
E, l
'g j%^ g l~
C
- d. Performance of an air
- d. 3 years
- d. BVT 1.1 - 1.3321
.O riow test through each Main FIIter Banks e
8VT 1.1 - 1.33.2
- 0. <
open head spray /
C Cnet. Cable Pen l
g sprinkler header to o
verify each open (SVT 2.1 - 1.33.1) e.*
l a
nozzle is unobstructed.
(SVT 2.1 - 1.33.2) en
,c%
.,l; " ' - j w
ll yc.e;i I
g. $' I j
gy+.r 4
.h3.?I j
Les ;p
.m
'~,
6'
'D r
t es.. ;
i O*
s e
T-o.
ai r
e, ;
i on e?
os 4
l A
- i
Il
\\i
, 4
.I l
s s.;
.+,
,,,---_,.,---,-.n-
~,-n-r
. = ~
TABLE 2 (P;ge 8 cr 11)
S v SI f_M R[QUlklMEN!
SuRylltLANCC RCQUIRLMLNI RCQUIRtD FRLQUENCY REFLRLMCL UNii 1 (UNif 2)
~
we M
'a, CO2 Jystem CO2 Systems serving the
- a. Verification of the
- m. Weekly
- a. OST 1.33.9 l
ro l l owi ng a rea s sha l l be associated CC2 (OST 2.33.9) l O
OPERAPLE:
storage tank levels &
8 c
pressures, 43 Unit 1 Areas:
b, Verification that the b.
18 months
- b. OST 1.33.13C l
g
- Cable f ray Mezzanine system (valves and (OST 2.33.13C) l *ms 02
- Cable Vaults associated dampers) 3
- Diesel Generator Rooms actuates manually &
n to e automatically upon Unit 2 Areas:
receipt of simuisted m
uE
- Cable Spreading Area signal.
B Control Bldg.
Instrumentation Room
- c. Verification or flow
- c. 18 months
- c. OST 1.33.13C
$l $7 Cont rol Bldg.
From each nozzle (OST 2.33.13C) re >=
- Communication Room durin9 a "purr test".
yn Cont ro l Bldg.
2
- Cable Tunnes Between Control & Aux. Bldgs.
pg p.<
E8
- Cable Tunnel Aux. Bldg.
- Cable Vault & Rod
%l#
oo W
Contro" Areas y) qs c M
- Cable Spreading Area 3
ha Se rvice Bldg.
r
- Emergency Diesel o,,
Cennrator Bldg. Room gf ch --~
08 8 5.
I're Hose Hose stations serving
'a.
Inspection or the fi re
- a. Monthly a.
OST 1.33.2 Stations the rollowing areas shall hose stations (OST 2.33.2) g be OPERABLE:
accessibl3 during
$"i plant operations to Unit 1 Areas:
assure all requ i red r*
- P ri ma ry Aux. Bldg.
equipment is at the M
Fuel Bldg.
station.
PJ Intake Structure l
- Service Bldg. ( Sa fe ty-b.1 Inspection or the b.1.
18 months b.1. OST 1.33.2
,s Related Areas) fire hose stations (OST 2.33.2) ts 2
- J-regua rds Bldg. ( Pi pe not accessible Turneet Areas) during plant
- Containment operations to assure CD all requi red equip.
Wnl. 2 Areas:
is at the station, o
Fuel & Decon Bldg.
l ps
- Diesel Generator Bldgs.
b.2. Removal or the hose b.2.
18 months b.2. OST 1.33.2
,, n i
u
. Cable Vault Areas &
for inspection and (OST 2.33.2) y l[
Relay Room re-rac k i ng.
y o
- Se rvice BIdg.
n l
7
- Aux. Bldg.
b.3.
Inspection of all b.3.
18 months b.3. OST 1.33.2 e
- Containment gaskets & replacing (OST 2.33.2)
U l
p l
- Control Ridg. & Cable any degraded gaskets v3 O
funnel in the couplings.
- Safeguards I
l l
_,-s
~
..A TA8tE 2 (Page 9 of 11) l Sy$1LM RLQUIREMENI
$URVLILLAMCL REQUIREMENT REQUIRED IRLQUENCY RLfLRENCE UNil 1 (UNii 2) ~ '*
N ee c.1 Partlas opening of c.1, 3 years c.1. OST 1.33.2 M
5, (cont enteed)
- each hose station (OST 2.33.2) o OST 1.33.130 (Seivice fM valve to verify O
valve operability &
Bldg. Hose Reel no flow blockage.
Stations)
'4 OST 1.33.30 (Cnet.
l.
c.2. Performance ol' a c.2. 3 years' Hose Reel Stations) h.
-8 gen hose hydrostatic c.2. OST 1.33.12 9.*~
test at least 50 psig above saw.
- 809 H :
(OST 2.33.2) ge e r i re ma in opera ting A8I hoses stored in k~
heated areas shall be m
pressure.
hydro-tested at least c: g 38
- every 3 years. All hoses stored outdoors or in unheated building e
a rea s sha l l be hydro-Q tested at least every an 18 months.
E te m
e G. Halon Systems Halon Systems protecting
- a. Verification that each
- a. Monthly
- a. OST f.33.20 O
(OST 2.33.18) g the fo l lowing a rea s sha l l valve (manual, power g,
be OPERABLE:
operated or auto) in W
the flow path is in
,o.
o Unit 1 Areas:
Its correct position.
C Process Equipment Area (Zone 1)
- b. Verification or Halon
- b. Semi-annual
- b. OST 1.33.22 Process [quipment Area storage (tanit weight (OST 2.33.18)
.e M
c.
z e
(Zone 2) greater than or equal
.s
- Cable tunnel (CV-3) to 95% or rull charge)
-g weight (or level) k H
Unit 2 Ares 3:
pressure greater than h-*
- Contrc e Bldg. Coeputer o r equa l to 90% of Room f ull charge pressure.
Q.
- Control Bldg. West Com.
9.'
Room
- c. Verification that the
- c. 18 months
- c. OST 1.33.23 (OST 2.33.20) system actesates
- O manually and automatically upon e ;
receipt or simulated to actuation sigr18 O
- d. Performance of a flow
- d. 3 years
- d. SVT 1.1 - 1.33.3 m'
1 0
(BVT 1.2 - 2.33.1) test to assure no
[l' f
blockage.
v 13 1 4
-e s J
a*
." Il o
.h f
- 2 i
- Ref T.S. Amendment No.18 (Fire Protection SER; dated Jiane 6. 1979).
e';,
f 4.; 1 5
I'!I I
w T "-+-
~
~n-,-~~-
TABLE 2 (P;ge 10 gr 11)
.3 2*
Sv51[M R[00 e REMElsi SUHvEILLANCE RtQUiR[MENI RIQUIRtD fRtQUENCY REFEREfgCE UNII 1 (USIli 2) w e
e-
' N. c 7, Fire Barrier All fire rated assemDIIes r.1 Inspection of the a.1 18 months a.1. SVT 1.1 - 1.33.5 o
Penetrations (walls, floor / ceilings, exposed surfaces or (SVT 2.1 - 1.33.5) 3~
cable tray enclosures each fire rated g
and other fire barriers) assembly.
N_
separating safety related g-fi re a rea s or sepa ra t ing m.2.
Inspection of" each a.2.
18 sonths a.2. SVT 1.1 - 1.33.5 aus 5 portions or redaandant fire window /rire (SVT 2.1 - 1.33.5) systems important to safe damper & associated
. e shutdown within a fire
.ea rdwa re, tm #
a res & a l l sealing devices In fire rated assembly a.3.
Inspection or at a.3.
18 months m.3. SVT 1.1 - 1.33.5 ta penetrations (fire doors, least 107,of" each (SVT 2.1 - 1.33.5)
Q rire windows, fire type (electrical &
4 3 dampers, cable & piping mechanical) of" tus e pene t ra t ion sea l s &
sea led penetration.
p#
ventilation seats) shall if apparent changes g
be Of'ERABLE (Units 1 & 2).
In appearance or abnormal degradations r
- W are round, a visuaI sus <
~#
M inspection of an additional 107,or E
.g w
each type of sealed b M y
penetration shall be
$ 8-made.
This e
Q inspection process p'
)
shall contImae until g
a 107, sample with no e
e e
apparent changes in appearance or l
abnormal degradatlon I,
is round.
,.y 1
b.1 Inspection or the b.1. Semi-annual b.1. OST 1.33.5 automatic hold-open, (OST 2.33.5) h*
release & closing i
mechanism & latches M
t of the required (Iro A
~
j doors.
J
~s C'
se b.2. Vert rication that D.3. Daily (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) b.3. OM 1.54.3, L3-1-2, e
each unlocked fire OL3-1-2,"L4-1-1 &
door without OL4-1-1 Fire Door o.
electrical Check" Logs 7
supervision is (OM 2.54.3. L14-1 thru g "Logs)
[o F i re Door
~
i closed.
Check g
,E v
4-M O
'e j
M 4
O M. -
3 i
.h Um w
i * 'y 1
r Q
O
.--J
... ~,
l
= %A e =e n,--
m.
---w-n
a
\\
t c.e..,ud
., ; c.
N,04'4 'n{o
! U.
I cr,t 6
91O9W<# *MOa9gCe4 W
h
& 'O ? c.> 7.. '
O'.
$ y,.?Ot a
e48 r*
r4 I e e
., < x
.,y
- h, jsQ'.9,t.
a C
M: a.4grM M 9 e,I Niii;;
n M
lg
)
2
, r i
2&o 1r l
- o o
M 11D 4o
^
U 1D
(
31 e L Lr e)
,4is,rs 1
L F g3.i g o Fo 3," L4" l t
i 421 U
5.11k25. 5"k M
E 1
c uC C
34eMre N
MLLhOhh E
OOOC(tC R
L 2
f L
R b
Y
)
C s
N r
E u
U o
Q h
L R
4 f
2
(
D L
y R
l I
i U
a Q
D E
R 2
b
)
1 1
ciee I
r M
tse o
L taar M
amef 1
E hol s
1 R
tteen urro i
na&ai e
u p,
o t
g Q
a E
ih sc P
R ttnmu aiesr
(
E c w pi t ons 2
C i
fs ab e
E W
irdho L
L rol c B
L eooer v,d h s o A
t T
Lv 3
Rus b
I M
L M(
d euQ L
R
)
M d
E e
T u
S n
r Y
i S
t noc
(
f
,#00 bw OM @
F <**.nD D=
d 0
r_
TAntE 3 (Page 1 cr 131 u
TIRE lleSURAreCE f ANil OPERA 88t_ITY REQUIREMENTS FOR FIRE PROTECTIO 88 SYSTEM q
NOTE:
Pr8or to removal of any major portion of the FPS or upon discovery that a es,jor piece of FPS equipment or section is out.
f9 --
o f-se rvice, the fire insurance carrier ( ANI) shall be notified (Refer to SAP 38).
M O u **
j EY$7EM REQuiREM(NT APf'LICABLJ. MODES CONDI180N RLQUIRED ACitOM 14ME REQU8RLMENT g ;i-M 'en
- 1. Fire Detection Instrumentatlon for Whenever the equip.
With the ntumber of Establish a fire Within is hours n
Instrumentation etch fire Zone that is being operable fire watch patrol at
-4 protecting non-safety protected is detection least once an hour g
related egulpeent operational or instruments less in the affected area v;
shall be operable, required to be than 50% of total whenever affected
. ~>
ope ra b le, a rea is unmanned.
Oy.
g'e M
Unit l' gk
- cuerdhouse g,.
- Alternate Access Facility e.e m.
c.. m
- ?
n&{:
~ H pam -
llt!J N'.gj I
PAF og :
'O Out Sides.
C.of
- EM Sub. Bldg.
Ek O
- Black D.C. Bldg.
- [RF j
os
- Training SIdg.
e.*
- Sloulator Bldg.
- Waste Mdig. Bldg.
. m '. 2
-[
- Admin. Bldg.
- Meteorological j
m Shelter
- s g.
l N
hE r*^
tus 4.s,A
^IO' SE!
9 7.
u e o Se
- 9 m
e ~ et.:
o
- . 6 pa-
- 9 O
O 'E@^
Q een. O --
4.n
. ~.; s w
c.
L.
j ii i(4 jl
!j
!;>)!5 i8 j, > :
iJ; i.
f-
+
..N, qs,sM Yt+
4':hf,hgWO9r%w'x tOj 3e,e-[ g kaEe fayg 7 o3[ g O.' vC,.
k<
n ERw$t.
~
e e
Ggp4 u A ' l '.y.O ? ;; o ',
4 8
. ke4i 4
_g Uo g n^kO d-gem $ go t
t 8
M e_
S*
8
~.
i t
s n
fE ru M
E s
o R
r h
R u
I s
U o
a Q
h E
n 5
i R
2 h
L n
A t
M i
/
i h
M W
4 I
t i
m b
W e
d h
e e
y
)
a c
)
s g
t n
t s
l r
l n
. p :,
a
(
i rl(
i 4
b 0
a f
uoa r
e a ui r
w s 4
r ore B fv e kt e
n e
I e
po htr
/ oe r ccdh) ae r C
p uta ea s
na aeetg rr a A
o k
e np nl tni bttan h3 o ocei sffd erewt@a cnr a d oeni d e
D o
aoa he ina ee yl t E
t bi hct tnzsrt d pf(t t
bl o.
S sd stc aoiuic i
f i
Qese@iae R
rsntfe veaam arre I
e wf erga f
os er tutf U
rs det l
rc b f
peotff roore soaf Q
ou i
E tt vpe aea Opcsoa Phtap Eh pa R
sa opf tr et ruf sio Rs Psa Eft a
b e
s t
l b
n a
a r
r d
e
)y.
p M
o ne 2he O
n al
(
l rb tb l
i da ona
]
l h
yr wer 0
i 1
D t
he tce N
a p
ap f
O p
eo yjo o
C nn ndn w
Oi AaI 2
o l
e F
s b
gaP
(
S 3
ED E
O L
M B
A E
s s
T L
e~
e B
p m
A i
l C
t t
l.
l l
N l
l P
a a
A t
t A
A e
t h
t eo l
a tlh p
nb ty e
s aadrt E
M oys rrear r
E ota detce ee ypa p R
l t
ffr hoiao u
aa c r Q
es eeosp E
l - d rbst d sese R
bne i
aot fl anek l
isc rna ealbuo e
l w
poe hhraot Otr Tsechs no
)
s
)
2 d eo is s
sesst s sm &g tttu g
eee d naeoe2d rtl;l ainHl l
psb B arci b&B M
pyas-edobta -
E uSctt rysorc1t T
S ii u AHsCal u
5 rl nO a CisO v
eepU de e pt r
S rtp d r r d s d pi d iaAon ainonAnn fW(ta YFaHa(Ua a.
b.
P 2
m8$ A" O" eo ME-WOD t
e TABLE 3 (Pcge 3 af 13)
Sf$i[M RE0utREMENT APPLICABLE MODES Cots 0l i s On REcusRED AcisOn TIME REQUIREMENT ca g '
~
- 3. Spray and/or The following water W.rever the equip.
One or more of the Establish an hourly Within as hours.
g Sprinkler System sprinkler systees bes.9 protened is selected porticns fire watch patrol in a
serving non-safety opera tiona l* o r in operable.
In the affected eras related areas shall required to be to check for proper I
be operable:
ope ra b le.
cooling, no ciI leakage, or'any
& :)
a >
Unit 1 Are13:
abnormal conditions,
^g I ~ >~.
- Turbine 81dg.
(MeZ2enine and M
basement floors)
Mf
- H2 Seal Oil Unit o p
- Lube Oil Reservoir 8
- Lube Oii Sto rage Room n
- Auw. Boller Room g
- Main Steen Pipe ge.
n Chase (opening from Turbine Qj Bldg.)
- Warehouse Ares N'
w b
- PCA Machine Shop 8
- Clean
- hop
- Cheelstry Lab gn#
- Guardhouse
, g m
. g:
- Yard Area
.g Q
Transformers Unit 2 Arces:
et s
- Turbine Sidg.
~ ~'
g (Mrzzanine and 0
besoment floor) 38, - p
- H2 Seal Oli Unit g Q
- Cisnd Stoss Exhaust
- fllters,
- Lube O f f Rese rvoi r
~~
(A
- Mein Steam Pipe
% :+
3] 7
- Pipe Opening to Weste Handling g
y.
p -t Sidg.
es _ 4
- Condensate Q _~ ~
Pol *shing SIdg.
- Weste Hdig. Bldg.
N
= HeeIth PtysIcs f
m Blog.
o ::r
.p as
- 5058 a e 4
- PAf
$3
- Dosfeetry SIdg.
. e o
- Schneider/Constr.
'd side.
[o e
- Yord Area Transformers e
M l
3, i
7 O
,,m,..-e.
- : v' W.
-4 s
- J
(
- ::a --- ;;;--- n ----
- m s -
..<; Nuclear.GroupfcySito Adminictrctive Proceder:sf3.,p
,ta w 2,; tid; y; Chapter;9Djy;,
TIRE. INSU3UM05 <(AMI)i,0PERABILITY REQUIREMENTS FOR, F.P,.S.yr:TABLEa 3 (p, age ;4 f f 10)
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25 TABLE 3 (Page 6 of 10) c n-Sy$llM REQUIRLMENT APPLICABLE MODES CON 0litON RLQUIRED ACilON IIHL R(QUIREMENT e;
l* !!
- 5. fire Hose Hose stations Whenever the equip.
One or more selected a.
Provide eatsivalent a. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
H O Stations servin9 the ir, the aress stations inoperable.
capacity backup
$Qc.
following r*on-safety prctected by the hose protection
'O re la ted a rea s selected stations is to the unpectected a rea if the shall be cperable; ope ra t iona l o r required to be Inoperable station
,o Unit 1 Ares _3:
ope.sSte.
i s the prima ry
,t=s u
means of fire a.n-
- t s* rb i ese o l dg.
g..;. jet 'on o n ttwr g.*
- Warehouse Ares a r rected a rea.
g y
- Wa te r T rea tment*
v n.
- Auw. Boiser Rs.
QR
- b. Establish an
- b. Within to hours.
O kC
- GuardNuse houriy fire ao :s watch patrol for M * * >*
Unit 2 Arma}:
the affected
- Turbine Oldg.
arem(s).
g
- Condensate N
- Polls %Ing Bldg.
h"r
- Waste Handling 4
r7 Bldg.
- Health Physics g ett ors V
Ares
- 5058 u
C O e
Q2mmon facilities p
O 6
Admin. Bldg.*
m
~,,
- PAF O'
- Offsite Warehouse
- Waste Handling cn j Sidg. ( Swi tchya rd )
y &
- $1mulator Biog.
78 j-E'
- if
!s,
.tn 5
s4.
D' eM 4
W a o Ptf E{s 00
'O e n oe cb et S
'k 8,
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' NOTE: Denotes areas where primary means or fire protection is fire hose racks.
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~ E TABLE 3 (Page 8 of 10) g
..me
- a s e SYSILM RI.QU I R LMthi APPLlCABLL MOOLS COMDillON REQUSHLD ACISOM IlML HiQUIREMCNT g 'a7r w o F.
Fire Barrier All fi re ra ted At mil times (unless One or more Establish an hourly Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- E M
O l ** 4 Penetrations assemblies testing or preventive I nope ra b l e, fi re watch for 1
and all applicable maintenance is being the a f fected a rea s penetra t ion sea l s perforleed on the whenever ttre I,,
(including fire equipment / area a f fected a reas n
doors, fire dampers, protected by CO2 or.
are unemoned, a es etc.) assoclated Halon which requires QE with areas protected the (Ere systee X
by total ricoding to be 0.0.5.)
O(
CO2 or Halon Systees 3
st sll be operable:
0
- 9 3 w Unit.1:
e
- Cua rdhouse (D.C.
q" -
Room CO2 System) m
- Guardhouse (CAS P~"
Room Pelon Systeel H 7
- Warehouse l&C Ne m
A fquip. Room (Holon System)
C g
(SAS Room ch, O
HeIon Syatem)
C
- PAF (Tele. Equip.
Room Halon System) a
- 3058 (Records Room Halon System)
- 5058 (Comm. Re.
Halon System) g N
Qgemon Facilities
'.4 *[
- ERf Substation ar g
Black DG Sidgs.
r (CO2 System) f
- [RT (Holon Systee)
,n :
- Sleulator SIdg.
I v.
t (Halon Systee) y _ f,,,
- Adeln. Sidg.
(Records Rooe) g.n l e-E n
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F 11NSURANCE (ANI) CFERABILITY REQUIREMDITS-FOR~ F.P!S2, 3 TABLE 3 (p:se 10 ef 10)
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te8 s-a Revision 5 Page 55 of 69
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TAst[ O (Page 1 cr 13) at FfPE INSvaAseCE fAstI1 SURVEILLAseCE PEQUI#E9eE4TS F08% FfPE PeOTECTIOel 3YSTEM
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l Sv5 TEM RC00lREMENI SURVElLLA8eCE REQutREMENT RE0ulRLD FRtQUCleCY RUERENCE timeI t (tiest i 2) iM
.O 1, fire Detection Instrumentation for each
- a. Each of the fire m.t. 6 months a.1. Unit 1f2):
N'o fnstrumentation fire Zone protecting detection instrueents OSI 1.33.36 gj con-safety reIated and the supervised (05T 2.33.16) j
- 4 ow lpeent shafi be circuits associated I
l ope rab le, with the detector a.2. Annual s.2. Qvt-Ofdgh:
alarms shaII be OSI 1.33.18 (Admin.
p l
Unft It demonstrated operable.
8 dg.)
ee OST 1.33.24: (ERF)
- Cuerdhouse i
OST 1.33.2S (Sim.
- Attornate Access Facility and Trng. Stdgs. )
M OST 1.33.29 (ERFS) nke O$
- PAF
..en en hE
,9, sub Bldg.
I gj l co
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i W
- ERT 4
ui
- Training Berg.
g-
- Simulator Bldg.
n-
- ideste Mdig. Bldg.
.o
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f l
- teeteorotogica 8 Shetter n
t e
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C'A 4
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fAntt 4 (Page 2 nr 10) 5 i
Sv$iEM RLQutRLM(MI suHvfil.iANCE Riou1RLMimi aloughto (sttoutmCY nie t Ritect uts t I t (ueelt 2) 4
..' 8
.. og P.a.
Fire Suppression Operable flow path to
- a. Vertrication that each
- a. Qisarterly
- a. Uni M (2):
4 et Water System non-Sa fety re i s ted a rea s, valve in the (sow path OSI l.33.18
'O to Units 1 & 2 position and perform
. J,-
i s ita its correct
[ CST 2.33.3)
(A.pficable t
and Oset-BIdgs. )
drain test _,
Ois q;-J Iqq s,1 g
0,-
OSI 4.33.24 en OST 1.33.76 i
ee
- b. CycIinq or each vs8ve
- b. Annies I
- b. OST 1.33.1?
in the (sow path.
(OST 2.33.12)
OST t.33.2%
f' 051 1.33.?6 m'y:
a O'S
?. b, Yard Area The fire hydrants shall
- s. Verify operability of
- a. 6 months
- a. OST V.33.4 F i re Hyd rants be operable and essociated hydrants and enstwe (OST 2.3 3.4 )
Ic$,
and associated hose cabinets and cart barrels are dry and N>
seose Cadinets hoisses property stocked, threads fiebricated.
j ' l *,
and Cart Hotsses
- b. Performance of a
- b. Annesst
- b. OST 1.33.4 (Applicah!e (OST 2.33.4)
'C.
to Units 1 & 2 hydrant ritish test
"=
.e and Otet-88dgs. )
and ve ri fy ba rre l integrity.
4 n
- c. Inspection and
- c. 6 months
- c. OST 1.33.5
!T g",
a.
inventory of hose (OST 2.33.5)
)II se cabinets and cart g~g_
e hotese s.
o De u
e ;
.e
&+
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TIELE 4 ( Page 3 af 13)
SYST[M REQUIRLM[mi SURVEILL.AseCC R[QUIRLM4I R[QUIRLD IRtQuiseCY RiftAt8eCC UN.-l 1 ( U98 t I 2 )
me -
+ e a
e-q
- 1. Spray and/or The following water
- a. Verification that each m.1, Monthly s.t. Unit It21:
Sprinkler System sprinkter systems valve in the flow path OSI 1.33.1 Q,. $
serving non-screty is in its correct (OST 2.33.1) oc re la ted a rea s sha l l be position.
9 operable; a.2. Quarterly a.2. O_qgt-Didesi:
Unit 1 Arees:
OSI 1.33.24 OST 1.33.26 Turbine 8163 (Merrenine end
- b. Cycl arvj of each b.
Anntial b.1. Un M R):
n basenent floors) testable valve in the OST 4.33.6
- M2 Seal Oil Unit flow path.
OST 3.33.f2
- Lube Olt Reservoir (OST 2.33.6)
M h.
- Lube Oil Storage Room (GST 2.33.12)
(
m
- Aux. Boi le-Room
> :s
- Mein Steen Pipe Chase b.2 9tzt-91641,1
%7 (opening tror Turbine -
OSI 1.33.24 lv n
OST 1.33.26 V g Steg.)
se m
- idershouse Aram
- PCA Machine $ ssp
- c. Perfortmance of a sys.
- c. 18 Months c.1. ynit t it}:
h "r
- Clean Shop functional test and i
Ost 1.33.6 g4 n
m
- Cheelstry Lab veri fying that automatic (OST 2.33.10m)
- Cuardhouse valves in the flow
- W g
- Yard Area Tra.isformers path actuate ca correctly.
e.2. Qvi-3 d m :
2 v
OSI 17, 3.24 e
U"It 2 AF'91:
OST 1.33.26 Om
- turbine 88dg.
,l (Mezzanine and e
besement floor)
- M2 Seel Olt Unit g,a
- ci.nd Steam t h..st n i t.rs
- Lube Oi! Reservoi r
. Mein Stener Pipe Chase 7
- Pipe Opening to waste Mendling Sidg.
se e if -
- Condenseto Po1Ishang
,;.W Sidg.
- t ' b '
l
- Weste Mandlig Bldg.
g '.,*-
8
- toes t th Pttysics Bldg.
re. ~
l
- SOS 8
'N t
- PAF
- Doslectry Bldg.
- Schne! der / Constriction
^
8189 g*
- Yard Area Transformers e n k
g a n g
N
,L
}
v 4..
.4 g
q A
e J ~. ~
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'*[.d TABl.E is ( Psge 5 or 10)
- -O.-
g Sv51LM REQUIRLMLHI SultVLll. LANCE HLQUlitLHLNI HLQulftLtJ l' REQ 8)LNCY HLILRLNCf. UNil 1 (UNii 2)
- n..
,%s s
O o M
n.
1 CO2 System The following CO2 Systems a.
Verification or the
- a. Weekly
- a. OST 1.33.9 t4 O se rv ing tion-Sa re ty Re la ted CCf2 storage tank level (OST 2.33.9 Q.$
4 Areas shall t>e operable:
& pressurn.
yI Enit 1 A rca_1:
b Verification that the b.
18 months b.1. gnlt 1[RJ:
m y
- lurbine/ Generator Area system actuates OSI l.33.10 ea (S Ten CO2 System) mantially and (OST ?.31.10) g
- Cua rdhouse (D.C. Room) automatically open g
recoipt or simulated b.?. Oudisfgh:
OM Un ij_( Ay a:
signal.
OSI 1.33.?9
'n
- lurbine/Cenerator Aren (7.5 Ton CO2 System)
- c. Pe/rormance or a c.
18 months c.l. Un~1 1(R):
a g U --
lv.7 "rurr inst".
OSI t.33.10 m
qssagn y cflities:
(OST 2.33.13n) n.
- Lit t Sanbstation Bldg.
g[Q
- TRr Black D.C. Dist l.
c.2. Otmiytgh:
o.
i OSI 1.33.29
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TABEE at (Page 6 or 10)
,.g; SYSILM REQUIREMENI SURVEIEt.ANCE REQU18tEMENI REQUIRED IREQUENCY l REFERENCE UNII I (018I 2) r.-
pa +
~
~
ry : e-
~g-.
.N
- 5. Fire Hose Hose statlons serving the a.
Inspection of the hose a. Anntta l
- a. OST 1.33.2 e_
O ' Of -
Stations rollowing non-sa'ety stations and associated (OST 2.33.2)
.. %'J@:
related areas shall be hose, inspection or ope rab le:
atI gasleets and Qtet-Gidos;
-g g'~
replacing any OST 1.33.25
,'~s ' #p M '
Unit 1 Ares.3:
degraded h ne or 2
- Turbine Bldg.
- Warehouse Arda
, k %'.
- Water T reatment b.
Par tially opening each b.
3 years
- b. OST 1.33.2 I
~ rt ?
- Aux. Bolla:r Roor.
hose station to verify (OST 2.33.2) l
.n'
- Cuardhouse va lve ope rabi l i ty and te -:
r*o riow bIockage.
Ot.enggn:
' 7 k 'i OSI 1.33.25
..~'
'. p. c :s Unit 2 Areas:
Turbine Bldg.
C*-
- Condensate Polishing
- c. Performance or a hose
- c. 3 years
- c. OST 1.33.2 Bldg.
hydro test.
(GST 2.33.2)
M" M
- Waste Handling Bldg.
08 '"
Ote t-B ldG s. :
n OST 1.33.25
@ r:
y
- Health Physics Area p
- 5058 w
~*~
g Coomon FacilItles:
r*.ao e
- Admin. 81dg.
I.E'
~
- FAI En C
- Orrsite Warehouse o-e.
- Waste Handling Bldg.
te;. g -
.n
- Slesulator 83dg.
~S
- SAPS Visitors Center
- SAPS T&T B143 eg6 A[, '.
. tn. u - 1
- e... ?> {.
I > 5 y
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=
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i
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^
' ?g
-n'
- -.._ w SYS1EM RiQUIREMENT SURVEtt. LANCE REQUIREMfMT REQUIRED FREQUfh0Y
. REFERENCE.thili 1 (t#Nii 2)
-yI$
...n.
t'o sq;g
- 5. ~4a t o.
Systems Haton Systeas protecting
- a. Verification that each
- a. Month!y
- a. OST 1.33.20 M-O'
. the followl.9 non-sarety va'Ive in the riov s,4ses (OST 2.33.1e) f,.@.
related creas snail be is in Its correcf.
2 ope rable, positfon.
g',ty ta
- A.? >.
Unit 1 Aress:
- b. Verification of Halon
- b. Annual
- b. Opt-8tdes.*-
- Guardhouse (CAS) storage & weight (or OSI 1.33.27 (Sim.
".gf,
~
- Wa ret-ouse (Equipment level) & pressure.'
Bldg.)
o, '
- g. g;4 I&C Room)
OST 1.33.18 (Admin.
- y Bldg.)
,..c g Unit 2 Areas:
OST 1.33.31 (ERF W-w;
- PAf (SAS) g a'
l v.i 7
- PAF (Tele. Equip. Re. ')
- c. Vertrication that the
- c. a.mua l
- c. OST 1.33.23 m
- S058 (Records Room) system actuates
( OST 2. 33.284 ) -
My g py -
- SO58 (Co.sm. Room) manually and automatically upon Oct-Bldas.:
c n
$&t-Bitos_.:
receipt of simulated OST t.33.27 ( Sim.
W :'
- i - ERF Rooms actuation of signal.
Bldg.)
hI
- O
- Simulator Bldg. Rooms OST 1.33.18 (Admin.)
m...
M
- Admin. Bldg. t R0 cords OST 1.33.31 ( ERF) u
- Room, g.
o e-e tug '. O.
- 3
. C l
W_n O
E:
c.<
$e.i.
w 14 u gP k
m
- h. I U,$
e
. tus.
.,o
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u.
4 s
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l
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l M
D' 4
- .. *O O.
rt Mt. 4
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e.
y O @
u 7.
y."'~.,
a a
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^'
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b TABLE 4 (PagO 8 of 10)
.[
..o Ha SYSTEn RLot,iRtHEhr SURVEILLANCE REQUIREHCNT REQutRED FREQUENCY ftEFERENCE UNil 1 (UNIT 2) g w et s --o All fire rated assemblies
- a. Verification that the a.1. 6 months a.1. ILn f t 1(2):
- 7. F8 ra Barrier and all applicable fi re doo rs a re OST 1.33.5 N -- C s%M' Penet ra tions l " gg 1
penetration seats operable and free (OST
- 23.5)
(including flre doors.
3 07 obstructions.
fi re dampers etc. )
n.2. f.nnual
.a.2. Out-Bldos :
l'A ;:
a g
OSI 1.33.25 associated with areas n ce '
protected by total
. M ' fD riooding CO2 or Ha f sn
%.y, Systems shall be operable
. o. ;
-g.h !
(Units 1 & 2).
O Unit 1:
-M**
M
- Cua rdhouse (D.C.
Room JO2 System) h N'
- Cum rdhouse (CAS g~$',
9-Room Halon System) g
~ Warehouse 4&C t-*'<'
- c Equip. Roop-(HaIon C;*-
g Syste*;
!E te <
o o'M Unit 2 t4 0;
- PAF {SAS Room
,p..
g Haton System) 0.l 0
- PAF (Tele. Equip.
Room Halon System)
- e i
- 5058 (Records Room
(# !
1 Halen System) p.< i e
- 5058 (Comm. Re.
g Halon System) l-
- 9',
s vs y ;
I Spemon FactiItles
, ;c
- ERf Substation &
et.{
Black DC Bldgs.
(CO2 System) ggt"* 4 ;
- ERF (Halon S'* stem)
+
- Simulator Eidg.
Ed & ' I j
(Haton System) t '.I :
y
- Admin. Sedg.
A {.+f:[E '
.cf (Retgrds Room) p*
iI, -I f oD.I.D ioi
- x8
{hN f
'o gi-r;.;
- e 4:
M Pt I '.
s*.
2 O
b; ',feh
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Nuclear' Group - Site Administrative Procedures
~
Chapter 9D
~
}
k.TACHMENT A
'i INSTRUCTIONS UPDATED FIRF. PROTECTION APPENDIX R REVIEW REPORT - BVPS UNIT 1 FIRE PROTECTION SAFE SHUTDOWN REPORT - BVPS UNIT 2 These instruccions define the methods and responsibilities for the initiation, review, approval and distribution of chenges to the BVPS Unit 1 Updated Fire Protection Appendix R Review Report and the BVPS Unit 2 Fire Protection Safe Shutdown Report.
INSTRUCTIO.SS l
1.
All proposed changes to the Fire Protection Reports shall be prepared utilizing the Fire Protection Report Proposed Change Form (Figure 1A).
2.
Personnel who present items for OSC review involving design change.s, l
procedures and NRC correspondence shall determine if the design changes or procedures affect the Unit 1 or Unit 2 Fire. Protection Reports and, if so, notify NED by forwarding a completed Preposed Change Form to the Nuclear Engineering Manager for processing with a copy of the OSC approved safsty evalua61on.
sequential reference number and shall coordinate 3.
NED shall assign a review of each proposed change. Review responsibilities are identiff.ed 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 CSC and ORC.
6.
NED shall coordinate word processing, reproduction and distribution.
l l
Page 66 of 69 Revision 5
m.-
yy};
j.-
. - ~,.
. -.. -. ~..,, _.,.
[.'
t
- i.
~
t
-)p, NdE. lear Group
, Site: Administrative Procedures
, Chapter 9D
. r L
(fr ATTACHMEhT A (continued)
Unit 1 Fire Protection Appendix R Review Report Sections Review Responsibilities Section
, Title
- PRI
- SEC SEC 1
IhTRODUCTION MNE
?!NS SLS 2.
HISTORICAL BACKGROUND MNS MNE SLS 3
UNIT DESCRIPTION MNE SLS FPE
'4-SHUTDOWN CAPASILITY SUtttARY PM MNS SLS 5
ELECTRICAL ANALYSIS MNE SLS FPE 6
RESOLUTION OF PROBLEM AREl.S MNE' SLS FPE 7
PROCEDURES (OM 560)
PM SLS FPE 8
IEEhTIFICATION OF HIGH/ LOW PRESSURE MNE SLS FPE SYSTEM IhTERFACES 9
UPDATED RESPONSE TO NRC STAFF'S MNE MNS SLS GENERIC LETTER 81-12 10 APPENDIX R REQUIREMEhTS J AND 0 (RCP MNE SLS FPE OIL COLLECTION AND EMERGENCY LIGHTING) 11 EXFllPTIONS MNS SLS FPE i
12 SCHEDULZ FOR COMPLIANCE MNS SLS FPE 1
i
- PRI - Primary Responsibility l
- SEC - Secondary Responsibility
.i I
APPENDIX R REPORT REVIEVER IhDEX i
i i
HNS - Manager, Nuclear Safety i
l SlJ - Senior Licensing Supervisor l
l FPE - Fire Protection Engineer MNE - Manager, Nuclear Engineering
?
PM - Plant Mana,wr (or Asst.)
l Page 67 of 69 Revision 5 t
i
.Y o
9 Nuclear Group - Site Administrative Procedures Chapter 9D l
ATTACHMENT A (continued)
(
TABLE 2A
{s ')
Unit 2 Fire Protection Safe Shutdown Report Sections Review Responsibilities Section Title
- PRI
- SEC SEC 1
IhTRODUCTION MNE tins SLS 2
FIRE AREA REVIEW MNE SLS FPE APPENDIX Al FIRE AREA DRAWINGS MNE SLS FPE kPPENDIXA2 EQUIPr!ENT AND COMPONENTS CONTROLLED PM MNS SLS FR0!! ALTERNATE SHlTTDOWN PANEL APPENDIX A3 CABLE MATRIX HNE SLS FPE APPENDIX A4 FIRE PROTECTION SAFE SHUTD0w'N 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 APPENDIN R PEPORT REVIEWER INDEX MNS - Manager, Nuclear Safety SLS - Senior Licensing Supervisor FPE - Fire Protection Engineer liNE - Manager, Nuclear Engineering PM - Plant Manager (or Asst.)
t Page 68 of 69 Revision 5 l
I
q.s,'/1 Ju
-h
'L NJclear Group - Site Administrative Procedures Chapter 9D I
b ATTACHMFNT A (continued)
FIGURE 1A PROPOSED CHANGE FORM APPLICABLE FIRE PROTECTION REPORT (check one):
O Updated Fire Protection Appendix R Review Report --BVPS Unit 1 O Fire Protection Safe Shutdown Report - BVPS Unit 2 TO BE CO?!PLETED 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:
4 I
Prepared By Date Reviewed by Date (DLC Supervision)
TO BE COMPLETED BY NED (Designated FPARRR Coordinator) i Reference No.
Date* Received NED (FPARRR Coordinator or designee)
Date Sent Out for Raview TO BE COMPLETED BY FIRE PROTECTION REPORT SECTION REVIEk'ERS:
No Comments Comments Attached Primary Dato Secondary Date O
O Secondary Date _.
O O
Heating No.
OSC Review Date ORC Review Date Mneting No.
Effective Date of Change:
Rev. No.
Page 69 of 69 Revision 5
.