ML20197G501
| ML20197G501 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/13/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GL-86-10, NUDOCS 8605160244 | |
| Download: ML20197G501 (40) | |
Text
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Pubhc Service Electric and Gas Corpany Ccrtin A. McNeill, Jr.
Pubhc Senace Electnc and Gas Company P.O. Box 236,Hancocks Bndge NJ 08038 609 339-4800 j
vice presider t.
Nuclear l
May 13, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing
Dear Ms. Adensam:
FIRE PROTECTION PROGRAM TECHNICAL SPECIFICATION DELETION HOPE CREEK GENERATING STATION DOCKET No. 50-354 Public Service Electric and Gas Company (PSE&G) requests the deletion of fire protection program elements from the Hope Creek Generating Station (HCGS) Technical Specifications when the full-power operating license is issued.
Since the fire protection program at HCGS currently meets the requirements of the existing Technical Specifications, no amendment to the present low-power license is being sought.
This request results in a significant improvement in the implementation of the fire protection program and based upon recent discussions with members of the NRC staff and guidance provided by Generic Letter 86-10 dated April 24, 1986, as well as precedence established by Cleveland Electric Illuminating Company for the Perry Nuclear Power Plant, should be acceptable to the NRC staff.
The fire protection program requirements currently defined in the Technical Specifications will be embodied within a periodic surveillance and test program at HCGS and entail a shifting of testing requirements from surveillance procedures to periodic test procedures.
'.. i effect, this will transfer fire protection program cc.nmitments, reporting requirements and amendments from the jurisdiction of 10CFR50.73 and 10CFR50.90 to 10CFR50.59 and 10CFR50.71(e).
Therefore, the fire protection program will be completely described and controlled through the HCGS FSAR and applicable procedures.
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B605160244 860513 1
g PDR ADOCK 05000354 p
PDR L
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J Director of Nuclear 2
5/13/86 Reactor Regulation i
In accordance with the conclusions reached in Attachment I
1, this request does not affect the ability of HCGS to l
achieve and maintain safe shutdown in the event of a fire I
and hence does not violate License Condition 2.C.(8), constitute j
an unreviewed safety question nor involve a significant hazards consideration.
Consistent with the guidance provided in Generic Letter 86-10, License Condition 2.C.(8) should be modified to include reference to this transmittal.
]
' contains the necessary FSAR additions while contains those Technical Specification deletions to support this request.
Should you have any questions, do not hesitate to contact us.
t Sincerely,
[
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j Attachments (5)
Enclosures (2)
I i
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D.H. Wagner USNRC Licensing Project Manager i
i R.W.
Borchardt i
i USNRC Senior Resident Inspector l
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ATTACHMENT 1 The existing HCGS Fire Protection Program is complete and has the necessary implementing features of the following controlling documents in place.
1.
Final Safety Analysis Report A.
Section 9.5.1 - Fire Protection Program B.
Appendix 9A - Appendix R Fire Hazards Analysis C.
Section 13.2.2 - Fire Brigade Training Program D.
Section 13.4.1.4 - SORC Responsibilities E.
Section 13.4.2.1.2.h&i - OSR Audits F.
Section 17.2.2 - Quality Assurance Program 2.
Technical Specifications t
A.
Section 3/4.3.7.8 - Fire Detection Instrumentation E.
Section 3/4.7.7 - Fire Suppression Systems C.
Section 3/4.7.8 - Fire Rated Assemblies D.
Section 6.2.2.e - Unit Staff E.
Section 6.5.1.6.1 - SORC Responsibilities F.
Section 6.5.2.4.3.h&i - OSR Audits 3.
Nuclear Department Procedures A.
Administrative (see Attachment 2)
B.
Emergancy Response (see Attachment 3)
C.
Surveillance (see Attachment 4)
D.
Periodic Test (see Attachment 5) 4.
Operational Quality Assurance Program The FSAR provides a general discussion of the fire protection, detection and suppression features as well as the fire hazards analysis, safe shutdown summary and comparison / deviation tables to 10CFR50 Appendix R.
The surveillance procedures implement the referenced Technical Specification requirements while the periodic test procedures implement surveillances for those portions of the fire protection program not included in the Technical Specifications.
Additionally, the emergency response procedures detail actions to be taken in response to various fire and medical emergencies including specific prefire plans while the administrative procedures control the overall functioning of the fire protection program.
In support of deleting the Technical Specifications from the fire protection program, the following criteria were developed and implemented.
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Page 2 1.
Surveillances to be incorporated in the new program must be consistent with those contained in the Technical Spec,1?ications (Procedure M10-FDD-005).
2.
A procedure mdst delineate what actions will be taken in the event of inoperable equipment or systems (Procedures M10-FDD-004 & -008).
3.
Administrative controls must ensure proper implementation and administration of the fire protection program
[ Procedures VPN-PLP-004 and SA-AP.ZZ-025(Q)].
An equivalent level of limiting conditions, remedial actions and surveillance requirements will be established in procedures M10-FDD-004, -005 and -008 to provide a level of protection equal to that described in the existing Technical Specifications.
FSAR Section 9.5.1.4.2 will be amended by incorporating a discussion of fire protection operations, testing and surveillances to address plant administrative procedures, periodic testing and remedial actions for inoperability.
Although these requirements are no longer controlled by 10CFR50.90, the jurisdiction of 10CFR50.59 will now apply and thereby assure future revisions and/or changes to the program are properly reviewed and approved.
In addition, the reporting requirements of 10CFR50.71(e) rather than 10CFR50.73 will assure proper staff notification when revisions are made to the program.
Based on the above discussion, it is evident that the fire protection program effectiveness will not change when the program elements identified in Enclosure 2 are deleted from the Technical Specifications.
The revisions to the HCGS procedures and FSAR serve to adequately reflect program commitments with the reporting requirements as identified above.
As a result it can be concluded that the request detailed in this transmittal does not affect the ability of HCGS to achieve and maintain safe shutdown in the event of a fire and hence does not violate License Condition 2.C.(8), constitute an unreviewed safety question nor involve a significant hazards consideration.
ATTACHMENT 2 ADMINISTRATIVE PROCEDURES NUMBER TITLE VPN-PLP-004 Fire Protection Program SA-AP.ZZ-025(Q)
Station Fire Protection Program M10-FDD-001 Fire Protection Organization M10-FDD-003 Fire Department Manning & Qualifications M10-FDD-004 Actions for Inoperable Fire Protection Systems M10-FDD-005 Fire Protection Periodic Durveillance and Test Program M10-FDD-008 Fire Protection System Impairments M10-FDD-009 Hot Work Authorization M10-FDD-013 Violation & Deficiency Reporting M10-FDD-021 Freeze Protection & Winterization of Fire Protection Systems M10-FDD-022 Fire Department Drills M10-FDD-023 Fire Department Training Program
t' ATTACHMENT 3 EMERGENCY RESPONSE PROCEDURES NUMBER TITLE M10-FRH-I-001 Control Room Fire Response 4
M10-FRH-I-002 Fire Department' Fire Response M10-FRH-I-003 Radiation Protection Fire Response M10-FRH-I-004 Emergency Medical Response M10-FRH-II ***
Safety Related Area Prefire Plans M10-FRH-III ***
Non-Safety Related Area Prefire Plans Where *** represents a specific pre-fire plan designated j
by building elevation and area.
The Roman Numeral II is used for safety-related areas whereas III is used to designate non-safety-related areas.
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ATTACHMENT 4 HOPE CREEK FIRE PROTECTION TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES NUMBER TITLE Operator Logbook Fire Water Storage. Tank Level Verification M10-SHk-002 Electic Motor Driven Fire Pump Operability Test M10-SHT-003 TS Fire Water Valve Lineup Verification M10-SHT-004 Fire Suppression Water System Flush M10-SHT-006 Fire Pump Annual Capacity Test M10-SHT-007 Fire Water System Valve Cycling Surveillance M10-SHT-008 Fire Main Flow Test M10-SHT-009 Weekly Diesel Driven Fire Pump Operability Test 901163 Quarterly Diesel Fire Pump Fuel Oil Sample MD-ST.KC-001(F)
Weekly Diesel Fire Pump Battery Test MD-ST.KC-002(F)
Quarterly riiesel Fire Pump Battery Test MD-ST.KC-003(F) 18 Month Diesel Fire Pump Battery Test MD-PM.KC-001(Q) 18 Month Diesel Fire Pump Engine Inspection M10-SHT-015 Water Spray & Deluge System Functional Test & Inspection M10'SHT-016 Preaction Sprinkler System Functional Test & Inspection M10-SHT-017 Preaction Water Spray System Functional Test & Inspection M10-SHT-018 Triennial Deluge Sprinkler Flow Test M10-SHT-019 17 Ton CO 2 System Flow Path Verification M10-SHT-020 17 Ton CO 2 System Storage Level & Press Verification M10-SHT-021 17 Ton CO 2 System Operability & Part Discharge M10-SHT-022 TS Fire Hose Station Visual Inspection M10-SHT-023 TS Fire Hose Station Detailed Inspection M10-SHT-024 TS Fire Hose Station Flow Verification M10-SHT-025 TS Fire Hose Station Hydrostatic Test M10-SHT-026 18 Month Fire Barrier Penetration Inspection M10-SHT-027 Fire Door Inspection Surveillance M10-SHT-028 18 Month Fire Damper Visual Inspection M10-SHT-029 Semi-Annual Fire Detection Operability Test M10-SHT-030 Semi-Annual Supervised Circuit Operability Test M10-SHT-034 Wet Pipe Sprinkler System Functional Test & Inspection M10-SHT-039 Emergency Lighting Equipment Test & Inspection M10-SHT-048 18 Month Halon System Air Flow Test M10-SHT-056 18 Month Fire Barrier Inspection M10-SHT-058 Roving Patrol M10-SHT-060 Preaction System 1PS4 Functional Test & Inspection M10-SHT-061 System 1D28 Functional Test and Inspection M10-SHT-066 Control Room Halon Level & Pressure Verification M10-SHT-067 Monthly Supervised Water System Valve Lineup M10-SHT-068 Monthly Supervised CO 2 System Valve Lineup M10-SHT-069 In-Duct Fire Detection Functional Test M10-SHT-070 18 Month Emergency Lighting 8 Hour Functional Test
ATTACHMENT 5 HOPE CREEK FIRE PROTECTION PERIODIC TEST PROCEDURES
- NUMBER TITLE M10-SHN-003 Fire Water Valve Lineup Verification M10-SHN-007 Fire Water System Valve Cycling Procedure M10-SHN-015 Water Spray & Deluge System Functional Test & Inspection M10-SHN-016 Preaction Sprinkler System Functional Test & Inspection M10-SHN-019 4 Ton CO 2 System Flow Path Verification M10-SHN-020 Storage Tank Level & Pressure Verification M10-SHN-021 4 Ton CO 2 System Operability & Part Discharge M10-SHN-022 Non TS Fire Hose Station Visual Inspection M10-SHN-023 Non TS Fire Hose Station Detailed Inspection M10-SHN-024 Non TS Fire Hose Station Flow Verification M10-SHN-025 Non TS Indoor Fire Hose Hydrostatic Test M10-SHN-027 Non TS Fire Door Operability Test M10-SHN-028 Non TS Fire Damper Inspection M10-SHN-029 Fire Detection Functional Test M10-SHN-032 CO 2 Hose Reel Inspection & Operability Test M10-SHN-034 Wet Pipe Sprinkler System Functional Test & Inspection M10-SHN-035 Foam System Functional Test M10-SHN-036 Fire Hydrant & Hose House Inspection M10-SHN-037 Outdoor Fire Hose Hydrostatic Test M10-SHN-038 Fire Extinguisher Monthly Inspection M10-SHN-040 Fire Alarm Pull Boxes - Functional Test M10-SHN-041 Guardhouse Halon System Functional Test M10-SHN-042 TDR Halon System Functional Test M10-SHN-043 Guardhouse Halon System Level & Pressure Verification M10-SHN-044 TDR Halon System Level & Pressure Verification M10-SHN-050 PBX Telephone Room Halon System Functional Test & Inspection M10-SHN-051 PBX Telephone Room Halon System Level & Pressure Verification M10-SHN-052 QA Vault Halon System Functional Test & Inspection M10-SHN-053 QA Vault Halon System Level & Pressure Verification M10-SHN-054 High Pressure CO 2 System Functional Test & Inspection M10-SHN-055 High Pressure CO 2 System Level & Pressure Verification M10-SHN-057 Outside Water Spray System Functional Test & Inspection
- Not identified / required by the Technical Specifications
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ENCLOSURE 1 a
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including automatic detection equipment, is fully tested for operative condition.
- 9. 5.1. 4.1. 6 Smoke and Fire Detection System The smoke and fire detection system is tested for correct operation and function in accordance with NFPA 72E.
9.5.1.4.2 Operational Testing and Inspection ll G ET W y
i Rcutinc curecillance testing of fire protecticr systcmc and equip cnt will be performed ir acccrdance with the applicable Occtienc Of the Technical Specification
' Chapter 15 "CCC FSAR)
Efer ecuirment installed is safety related reac of the clant.
1 Routine surveillance testing of the fire protection system in non-safety related areas of the plant will be performed in accordance with the applicable NFPA design and installation standards as modified by the performance history of the equipment and equipment accessibility.
Y Yire barrier penetratienc are inspected periodically in t
accordance with technical cpecificatione to accertain penetration integrity 9.5.1.5 Orcanization Personnel Oualification and Trainina 9.5.1.5.1 Fire Protection Organization and Personnel Qualifications The Vice President
- Nuclear has ultimate responsibility over the Hope Creek Fire Protection Program.
The General Manager - Nuclear Services shall establish overall policy relating to the fire protection program and shall coordinate overall fire protection support from Nuclear Support, Hope Creek Operations and Quality Assurance, a.
The Manager - Nuclear Site Protection will formulate specific fire protecion policies and will develop, implement and check compliance with the fire protection d
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9.5-36 Amendment 12 s
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INSERT FOR PAGE 9.5-36 Administration controls are provided through existing Nuclear Department, Site Protection and Hope Creek Station Administrative Procedures, Station Operating Procedures and the Operational Quality Assurance Program to ensure that the Fire Protection Program and equipment is properly maintained.
This includes QA audits of the program implementation, conduct ~of periodic test inspections, and remedial actions for systems and barriers out of service.
This program emphasizes those elements of fire protection that are associated with safe shutdown as described in Appendix 9A and their significance when evaluating program and equipment deficiences.
All fire protection equipment and systems are subject to l
a complete inspection and acceptance test in accordance with the National Fire Codes after installation is completed.
After the plant is in operation, periodic inspections and tests will be conducted as defined by the Fire Protection Program and National Fire Codes.
The following fire protection features will be subjected to periodic tests and inspections:
A.
Fire alarm and detection systems j
B.
Wet pipe automatic sprinkler systems C.
Water spray systems D.
Preaction water spray systems E.
Preaction sprinkler systems F.
Carbon dioxide total flooding systems G.
Local application carbon dioxide systems H.
Halon systems I.
Foam systems J.
Fire pumps K.
Fire barriers (walls, fire doors, penetration seals, fire dampers)
L.
Manual suppression (fire hoses, extinguishers, hydrants)
Equipment out of service, including fire suppression, detection and barriers, will be controlled through the administrative program and appropriate remedial actions taken.
The program requires all impairments to fire protection systems to be identified.
Based on the condition, engineering analysis may be required to determine the extent of the fire hazard to safe plant operations.
As conditions warrant, remedial actions would include compensatory measures to ensure an equivalent level of fire protection in addition to timely efforts to effect repairs and restore equipment to service.
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ENCLOSURE 2 O
--2N INDE)
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATICh............
3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATI0h.................
3/4 3-5 3/4.3.3 EMERGENCY CORE C00 LING SYSTEM ACTUATIch INSTRUMENTATION......................................
3/4 3-3:
3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pumo Trip System Instrumentation..
3/4 3-41 End-of-Cycle Recirculation Pumo Trip Syste.
Instrumentatier.......................................
3/4 3-45 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATICh......................................
3/4 3-51 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATI0h....................
3/4 3-55 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................
3/4 3-62 Seismic Monitoring Instrumentation...................
3/4 3-68 Meteorological Monitoring Instrumentation............
3/4 3-71 Remote Shutdown Monitoring Instrumentation and Controls.............................................
3/4 3-74 Accident Monitoring Instrumentation..................
3/4 3-54 Source Range Monitors................................
3/4 3-83 Traver, sing In-Core Probe System......................
3/4 3-89,)P '
I fi rc Oetection Instru.mentatica.......................
3/4 3-00 I Loose-Part Detection System..........................
3/4 3-98 l
Radioactive Liquid Effluent Monitoring Instrumentation......................................
3/4 3-99
-Radioactive Gaseous Effluent Monitoring I n s t r um e n t a '. i o n......................................
3/4 3-104 3/4.3.8 TURSINE OVERSPEED PROTECTION SYSTEM..................
3/4 3-111 3/4.3.9 FEE 0 WATER / MAIN TUREINE TRIP SYSTEM ACTUATION INSTRUMENTATION......................................
3/4 3-113 MCFE CREEK vi APF i GSS
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INDO LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENT3 SECTION PAGE 3/4.7 PLANT SYSTEM 3 3/4.7.1 SERVICE WATER SYSTEM 3 Safety Auxiliaries Cooling Systen..........
.......... 3/4 7 ~.
Stati on Se rvi ce Wate r Sys ten.........................
3/
- 7-3 Ultimate heat Sinr....................................
3/4 7-5 3/4.7.2 CONTROL ROCM EMERGENCY FILTRATION SYSTEM.............
3/
- 7-6 3/4.7.3 FLCOD PROTECTION........................
3/4 7-9 3/4.7.4 REA~ TOR CORE ISOLATION CCOLING SYSTEF.................
3/4 7-11 3/*.7.5 SNUEEERS.............................................
3/4 7-13 3/4.7.6 SEALED SOURCE CONTAMINATI0h..........................
3/4 7-19
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3.4.7.9 MAIN TURBINE BYPASS SYSTEM...........................
3/4 7-33 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources-Operating..'.............................
3/4 8-1 l
A.C. Sources-Shutdown................................
3/4 8-11 3/4.8.2 D.C. SOURCES D.C.
Sources-Operating...............................
3/4 8-12 D.C.
Sources-Shutdown................................
3/4 8-17 f
HOPE CREEK ix APRi1.-~~a;3 i
97 INDD BASES SECTION PAGE INSTRUMENTATION (Continued)
Seismic Monitoring Instrumentatier...............
E 3/4 3-4 Meteorological Mor.itoring Instrumentatier........
5 3/4 3-4 Remote Shutcown Monitoring Instrumentation and Controls..................................
B 3/4 3-5 Accicent Monitoring Instrumentatier..............
B 3/4 3-5 Saurce Range Monitors...........................
B 3/4 3-5 Travarsing In-Core Probe Systen.................
E 3/4 3-E,P
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Loose-Part Cetection System.....................
B 3/4 3-5 Radioactive Licuid Effluent Monitorin; I nstrume nta ti o n...............................
B 3/4 3-6 Radioactive Gaseous Effluent Monitoring I ns trume ntati on...............................
B 3/4 3-7 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.............
B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...............................
B 3/4 3-7 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 kECIRCULATION SYSTEM............................
B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES............................
B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE
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L,eakage Detection Systems.......................
B 3/4 4-3 Operational Leakage.............................
B 3/4 4-3 3/4.4.4 CHEMISTRY.......................................
B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY...............................
B 3/4 4-4 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.....................
B 3/4 4-5 3/4.4.7 MAIN STEAM LINE ISO LATION VALVES................
B 3/4 4-6 3/4.4.8 STRUCTURAL INTEGRITY............................
B 3/4 4-6 3/4.4.9 RESIDUAL HEAT REM 0 VAL...........................
B 3/4 4-5 HOPE CREEK xiv 2LL
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9b7 INDEF BASE 5 SECTIO'.
PAGE PLANT SYSTEMS (Centinued) 3/4.7.5 SEALED SOURCE CONTAMINATI0h.....................
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3/4.7.9 MAIN TURBINE BYPASS SYSTEM......................
B 3/4 7-E 3 /4. E ELECTRICAL POWER SYSTEM 5 3/4.E.1, 3/4.8.2 and 3/4.e.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMI............................
B 3/4 E-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.........
B 3/4 E-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 R EACTO R MOD E SWITCH............................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION..........
B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION............................
B 3/4 9-1 3/4.9.4 DECAY TIME......................................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS..................................
B 3/4 9-1 3/4.9.6 REFUELING PLATF0RM..............................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L............
B 3/4 9-2
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3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L.......
B 3/4 9-2 I
3/4.9.10 CONTROL ROD REM 0 VAL.............................
B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY...................
B 3/4 10-1 3/4.10.2 RCD SEQUENCE CONTROL SYSTEM.....................
B 3/4 10-1 3/4.10.3 SHUTCDWN MARGIN DEMONSTRATIONS..................
B 3/4 10-1 HOPE CREEK xvi
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6/M IN3TRUMENTATICN FIRE DETECTION INSTRUMENTATICS LIMITING CONDITION FOR OPERATICS 3.3.'.S As a minimum, tne fire cetection instrumentation for eacn fir cetet n zone snewn in Table 3.3.7.8-1 shall be OPERAELE.
APPLICAERITY:
knenever ecuio ent protected by tne fire detectier/instrumen:
1s recuire* to be OPERAELE.
ACTION:
a.
Witn 4.e nuccer of OPERAELE fire cetection instruments in one er
- re 2crec:
1.
Less than, but ecre tnan one-half of, th Total Nu:ber of Instrt..ents shown in Table 3.3.7.8-1 fo Function A, restore the inc erable Function A instrument (
to OPERABLE status within 1* days or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> esta ish a fire waten catrol to inscect tne zone (s) Lith the in erable instrument (s) at least once o r neur.
2.
One less than he Total Nuccer f Instruments shown in Tacle 3.3.7.8-1 *ar Function ~, or one-half or less of the Total Nuccer of Instrue. ts shown Table 3.3.7.8-1 for Function A, or with any two or. ore ad' cent instruments inocerable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a e' w tch patrol to inspect the Zone (s).with the inocerable instru,.. rh(s) at least once per hour.
9 b.
The provisions of Specific i
s 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS
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4.3.7.8.1 Each of the abov recuired fire detec ion instruments which are accessible curing unit op ation shall be demonsti ted OPERABLE at least once per 6 months by performa se of a CHANNEL FUNCTIONAL EST, except for restorable spot type heat cetector, which will b'e tested such t at at least one cetector or. eacn signal-initia ng circuit will be tested at le t once per 6 months, such that all detec+ rs are tested in 5 years.
Fire cet ctors which are not accessible during it coeration shall be demonstrated OP BLE by the perfor-mance of a CHANN FUNCTIONAL TEST,du ng each COLD SHUTD0k exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
unless perfome in the previous 6 :o hs.
4.3.7.8.2 Th NFPA Standard 72D supe ised circuits supervisio associated with the c~e ctor alarms of each of th above required fire dete qion i
instrument shall be demonstrated OPERABLE at least once per 6 mon hs.
HOPE CREEK 3/? 3-50 APP. I : T
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inBLE 3.3.7.0-1
,o A
flRE DEI CTI0il IllsilurrfirirAi10rl S
DELE IJON h
ZONE ELEV.
R00H OR ARfA (flRE 10NE/R00l l 11 0., )
lIfAI ftAvE Sf'0K E a.
Reactor iIldinD 4101 54' RilRIumpRoom(4114)
II/A.
H/A 6/0 4102 54' ilR Pump l3) il/A' il/A 4/0 Rifb ur.p/ lit. Exch. Room (41 4103 54' Room and CRW/ORW P nrp Roan (410r, A If/A fl/A 8/0 4107)
/
4104 54' RilR Purp 1 Exch. Room (41 19)
,/
ll/A fl/A 4/0 CoreSpray(t.
4105 54' Fqmp Room (4116) il/A tt/A S/0 4106 54' Core Spray pub;(Room (4110) ll/A ft/A S/0 4107 54' Core Spray Pump Room (4105) il/A il/A 6/0 4100 54' Core Spray Pump Roo (4104) il/A il/A 5/0 4109 54'
<llPCI Pump & Turbine Ro g (4 tll) il/A fi/A 6/0 io 4110 54' HCICPump&TurbineRoomyQ l}0 H/A fl/A J/0 w
4111 S4' Electric tquipment. noc: (4j g'1 n/A 7 /A G70 ip 4112 54' Electric Equipment Room,{'41)0)N-il/A ll/A 3/0 ft/A fl/A 6/0 m
4102 77' RilR lleat Exchanger Roc 6 (4214) 4104 77' RilR lleat Exchanger (nom (42 30)
\\
N/A fl/A 3/0 4201 77' RACS Pump /lleat ch. Area P issage (471t, 4709, N/A fl/A 10/o 4213)
\\
4201 77' Safeguajri)instrumentRoon(
Safeguard strument Room ( 1210) fl/A fl/A I/O 1219)
\\ fi/A 4201 77' il/A 1/0 4202 77' HCC Arfa (4215)
Nil /A il/A 4/0 4203 77' HCprea(4205) li/
II/A 4/0 4203 77' assage (4207) fi/A il/A 2/0 4204 77' HCC Area & Corridor (4210, 1216)
II/A N/A 10/0 4205 77' HCC Area (4201) 0/0 ft/A 7/0 4206 CR0 Pumps Room 2 Corridor ( 1202 & 4201) fl/A N/A 9/0 4301 102' SACS lleat Exch./ Pump Room ( 1309) ll/A il/A 20/0 s
4302 102' HCC Area & Corridor (4310, 1301) 0/ l'i fl/A 14/0 4303 102' SACS Ileat Exch./ Pump Room ( 1307) il/A N/A 10/0
'.~.
4 (r 102' HCC Area and Corridor (4303 )
N/A fl/A
/0 9(/0 305 102' Equip. Airlock (4323) il/A il/A 4306 102' CR0 flydr. Control Area (432 1) fl/A fl/A 4/0 k.
e
- l A
TABIE3.1.7.0-1(Continued) ci el flRE DEifC (1011 lilSTRin1f fil AIInft h
DETEC1 f(
'A' 20tlE N ELEV.
R00H OR AREA (FIRE 70flE/R00ll110 1 lifAI fl AfjE SP'0K E
\\
li7v)
G7v)
(UM a.
Reactor Bull inD (Cont'd) s 4306 102' (q. & Equip. Access Area & Corridor II/A[
II/A 7/0 (433 4315) 4306 102' CR0 R al & Repair Area (4316, 4333)
};/A il/A 3/0 4107 -
102' CR0 llyd nd Haster Control areas and Equip.AccehArea(4317,432l1,4322) ll/A ti/A 11/0 4401 132' FRVS Recirc. Im t Area (4410) ll/A il/A 7/o Compr.&Elec.E(qupArea& Corridor (4101, 4402 132' il/A fl/A 13/n 4400)
/
4403 132' FRVS Recirc. linit Are 411, 4412 A 111) il/A fl/A 9/0 4404 132' Elec. Equipment Area (44 1 4<l0 ti/A ti/A 11/0 i>
45(L1 145' Elec. Equipment Area (450tha )
il/A il/A 9/o
-~~
4 4502 145' Passageway (4504, 4508)
/
ti/A ti/A 11/0 4601 162' FRVS Circ. linit Room (46JA) il/A tt/A 7/0 g
4601 162' FRVSCirc.UnitRoom44615) il/A ll/A 6/0 4602 162' Equip Area 2 Corridpr (4605, <l608) x fl/A fl/A 14/0 4602 162' Pos t-LOCA Recomb. Area (4604, 4602, il/A fi/A 0/0 4701 170'-6" Platform Area ll/A ti/A 5/0 4701 170'-6" FRVS Recirc Init Room (4616) il/A fl/A 0/0 4701 170'-6" FRVS Reci
. Unit Room (4617)
!!/A ti/A 6/0 4308 102' Drywe ccess Room (4330) ll/A fl/A 3/0 4309 102' Heu n Honitoring Sys. Area 4310)
II/Ah fl/A 3/0 4603 162' Fu Pool Cooling & lleat Exch Rooms fl/A N
ft/A 0/0 4625, 4626, 4627, 4620)
\\
4604 162' Standby Liquid Control Area (<l606)
N/A tt/A 5/0 4113 5-7 Torus Area Safe Shutdown Cable Trays, 4/0 il/h fl/A Channel A 4114 54/77 Torus Area Safe Shutdown Cable Trays, 4/0 ft/A ft/A Channel 0 26 41 54/77 Torus Area Safe Shutdown Cable Trays, 2/0 ft/A tt/A o
Channel C 4116 54/77 Torus Area Safe Shutdown Cable Trays, 2/0 ti/A ti/A Channel 0 in 4001 201' tiew f uel Storage Area and Lay'fown Area fi/A fl/A 3/0 h-(4706, 4700, 4710)
\\
L.
TADIE3.3.J.0-1(Continued}
f I Rf _ Of Tf C T INI _IllSIRHitI flTAl loti O
DE1[Ci Q l4 20flE N ELEV.
R00H OR AREA (flRE 20llE/R00!! fi0. }
llEAT IIAllE Sff0KE
^
N-Uc79) li79)
{T/i) b.
Auxiliary iib IdinD Control & 0/G Areas 3101 54' E(eKricEquipmentRooms(5129,5130) ectrio Equipment Room (5102) il/A ti/A 11/0 1101 54' l
il/A il/A 4/o 1103 54' 250V D 250VD(DDattery Rooms (5104) ti/A II/A 2/0 i103 54' C
Rp5 HG Se (ttery Rooms (5128)
II/
ll/A 2/0 t104 54' tA a (5105)
/A il/A 2/0
$105 54' DSL Full Sto.
nks Room (5107; 0/1 2/0 2/0 5'06 54' DSL full Stor. I n s Room (5108:
0/7 2/0 2/0 DSL full Stor. Tan (kh oom (5109:
5197 54' 0/7 2/0 2/0 5100 54' OSL Full Stor. Tanks (5110 0/7 2/0 2/0 5109 54' Controlled Stor. Area (5 0 )
fl/A it/A 11/0 5201 77' Cable Spreading Room (5202 II/A fl/A 0/27 w2 h202 77' il1V_Egul;L_ Room (s700) fil^
fi/A __.._ Slo._ -.
5203 77' il&V Equip. Room (5209)
II/A II/A 5/0 m
a 5204 77' il&V Equip. Roore (5210) ll/A il/A 5/0 w
5205 77' il&V Equip. Room (5211) ti/A fl/A 5/0 5206 77' Corridor (520/)
0/7 ft/A 3/0 5206 77' Corridor (5237) 0/12 ll/A 0/0 5207 77' Corridor (5215) ll/A it/A 1/0 ilA 77',
Wing Area S I and Exhaust Ourts it/A fl/A 3/0 (5215, 53 535) 5301 102' Cont r)0 Equip. Room (5302) ll/A N
ti/A 30/0 5314 102' DSL,&enerator Room (5304) 0/7 N2/0 1/0 5115 102' tSC Generator Room (5305) 0/7 2/(1 1/0 5316 102' SL Generator Room (5306) 0/7 2/0' 1/0 i
5317 102' DSL Generator Room (5307) 0/7 2/0 1/0 5318 in '
Elec Access Area (5301) fl/A Il/A g/0 5310 02' Electrical Access Area (5339) 0/26 fi/A 87 N
5319 102' Corridor (5315) il/A fi/A II/I l
- N 5401 117'6" Control Equip. Room Herz. (5403; 0/14 ft/A 22/0 Sill 124' Class IE Inverter Room (5447) il/A fl/A 1/0
'402 124' Class IE Inverter Room (5440) il/A fl/A 1/0
.i n.,
R un u
u
f j
/
s TABLE 3.3 7.0-1 (Continued) 5
~
el FIRE DETECT [0fl fil5TRI'f ff fliAIInfl DETECil0\\
A 20NE G EV.
R00H OR AREA (flRE 20ilE/R00tlflu.)
llEAT fl AllE / Sf'OKE V
(i70)
Ti7ET Ti79) b.
Auxiliary DuM ing Control & 0/G Areas (Cont'd)
\\
5407 124' Co Idor (5401) 0/9 ti/A 6/u 5403 130' 0/G trol Room (5410) il/A fl/A 1/0 5403 130' Class wgr. Room (5411)
II/A ti/A 3/0 130' D/G Contr Room (5412) n/,A (1/A 1/0 5404 5404 130' Class IE Swg Room (5413)
N/A il/A 3/0 5405 130' D/G Control Roo (5414) ti/A fl/A 1/0 5405 130' Class IE Swgr. Roo 5415) il/A ti/A 3/0 0/G Control Room ( N( Q )
5406 130' 541 tt/A ti/A 1/0 5406 130' Class IE Swgr. Room (511 ti/A ti/A J/0 5501 137' Conference and Storage Ro (b50,0 5520, 5571) ft/A fl/A 3/0 mh 5501 137' Corridors (5502, 5503, 5507,
?)f,5577) il/A rl/A 5/0 5502 137' Control Hoom and Heady Room y
w4 (5509, 5510, 5511) il/A it/A 15/c 5503 137' Control Rcom Computer (55l5) il/A fl/A 6/0 5504 137' Control Room Console N/A fl/A 0/0 5505 137' Control Room Vert.
ard (Rigir )
fl/A il/A 4/0 5506 137' Control Room Ve Board (flidd'e) fl/A fl/A 3/0 5507 137' Control Room y L. Doard (lefti N i/A ft/A 4/0 f
5515 137' Elec. Acceys' Area (5501)
N(A fl/A 5/0 5516 146' Datter har9er Room (5530) il/A il/A 2/0 5516 146' Datt Room (5539) ll/A ll/A I/O
\\
5517 156' Da}t ry Charger Room (5540) il/A il/A 2/0 5517 146' 6ttery Room (5541)
II/A 41/A 1/0 5510 146' Dattery Charger Room (5542) ll/A ti/A 2/0 5510 14 Dattery Room (5543)
N/A il/A'N 1/0 55'9 (6'
Dattery Charger Room (5544) il/A ft/A \\ 2/0
'3519 146' Dattery Room (5545) il/A il/A
\\l/0 55/1 77',
Elec. Cable Chase, Channel 0 (!'203, 0/15 ft/A r70 102',
5323, 5331, 5405, 5419, 5531) 3 124',
7
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T,A[Il f 3. 3. 7.fl-1(Continucci)
_Ill5T Rll!! fill Ai10fl FIRE DEIECI101 <
,h DETECT 10ft Z0llE RV.
R00H OR AREA (flRE 20flE/R00flfl0.]
IlEAT fl AffE
[51'0KE N
G79) 5 791 /
U79) b.
Auxiliary Dulld 0 Control & 0/G Areas (Cont'el)
Inver(tequih. Room (5620) 5615 163'6" llVA ll/A
/ ft/A 9/0 5616 163'6" Room (5621) ll/A fl/A 1/0 Inverte (r N (om (5622) 5617 163'6" ll/A II/A 1/0 5617 163'6" Inverter Roow (5623) il/)
il/A 1/0 5610 163'6" inverter Room (5624) if/A II/A 1/0 5619 163'6" DatteryRoom(5616
[il/A Il/A il/A 1/0 5619 163'6" Dattery doom (5627) fl/A 1/0 5620 163'6" Inverter Room (5628) il/A fl/A 1/0 5701 178' ilVAC Equip. Room & DSL Ar a fi/A ti/A 21/0 llVAC' Equip. Room (5703,570))\\
e 5702 178' Corridors (5702) il/A lt/A 5/0 J.
540()
130' U/U Air intake (542J, 5450)
II7A TI7A i//H to y
c.
Intake Structure 7115 93',
intake Struct. Unit 1-
& C Serv. Ut r.
0/2 il/A 9/0 7
122' Pumps (203,204,3py,306) 7116 93',
Intake Struct, dt 10 & D Serv. Wtr.
N /2 fl/A 9/0 122' Pumps (207, 311, 312) 7115 114' Intake Str
. Travelling Screen !!ator Area ll/A tt/A s/0 al.
Charcoal filter Units x
Reactor Dullding 13 '
TRVS Rectrc. Charcoal filter Corf artment 1/0 t1/A
.fl/A (2 '
FRVS Recire. Charcoal filter Comr artment 1/0 ti/A II/
h4-145' TRVS Vent Unit Charcoal filter Compartment 1/0 ti/A fl/A N"
145' FRV5 Vent Unit Charcoal filter Compartment 1/0 ft/A fl/A
~
162' TRVS Recirc. Charcoal filter Compartment 1/0 fl/A fl/A 162' TRVS Recirc. Charcoal filter Compartment 1/0 ft/A il/A 170'6" FRVS Recirc. Charcoal filter Compartment 1/0 ti/A fl/A h
f,}
170'6" FRV5 Recirc. Charcoal filter Compartment 1/0 ti/A fl/A v,
y+
/
/
M DIE 3.3. 7.0-1(Continu<pl)
/
l}
FIRE OfIICil Ofl_Irl51 Ultiti til A lloti DEifC L0ff n
l" 10flE ElEV.
R00fl OR AREA (FIRE 10llE/fl00llfl0.)
llEAI f L At!E al'0KE E70)
F/H
( /s) e.
Auxiliary uilding Control Area 153' h ontrol. Room Emerg. Char. filteh tinits 1/0 1/A fi/A 153' ntrol' Room Emerg. Char, filtc lini t s 1/0 ti/A t;/A f.
Auxiliary Guilding R aste & Service Areas x
3104 54' Corridor '(4110) ti/A 9/o Electrical hc ess Area (3204) 0/19 ti/A 0/0 3203 77' ElectricalAc(ces(sArea(3425) 3307 102' Area (3314) ti/A ft/A 3/0 3410 124' Electrical Acces 0/5 ti/A 4/0 3312 102' Corridor, Lobby & Vest ibule ll/A il/A 17/n t
(3301, 3302, 3304, 3313) 3312 102' Janitor's Room (3304)
N/A fl/A 1/0 mg 3312 102' ilot Water lleater Room (3342 ft/A fl/A 1/0 3113 102' Hen's-To l let--Rrr(-3303 )
-tl/A --
ti/A 170--
m 4
3400 124' Equipment Removal Area (34 ft/A il/A 7/0 N
3400 124' Controlled Locker Area & : rridnr il/A fl/A 3/0 (3443,3444)
'N 3400 124' Clean Issue Room (3JO )
il/A fl/A 1/0 3409 124' Uncontrolled Ha V. locker Area fl/A fl/A 4/0 s
Corridor (340 113)
'x 3503 137' RemoteShutj n Panel Room (3576)
'll/A
!!/A 7/0 3504 137' lincontrol ed Laundry and Towel Storage (3506, ll/A il/A 1/0 y
3500)
N 3519 137' TSC)) stibule and Radio Equiprmit Room (3579, fl/A N
ll/A 3/0 3r U N
3604 155'3" I&V Equip. Room (3606)
II/A li/4 6/0 3605 155' il&V Equip. Area (3605)
N/A fl/A'\\
4/0 3610 1
3" TSC Electrical Room (5619) il/A fl/A y 2/0 ti/A 55'3" Service Area Exhaust Duct (3605) il/A il/A N1/0 M
ll/A 137' & Service' Area Supply Duct (3555, 3609) il/A fl/A 2'/0
- o 155'3" fl/
124' & Solid Radwaste Supply and Exhaust Duct (3457 &
il/A fl/A 7/0 137' 3500) in 3 ( w/y):
is number of function A (early warning fire detection and notification only) inst ruments.
x y is number of function 0 (actuation of fire suppression systems and early warning notification) instruments.
lVf? /
PLANT SYSTEM-3/4.7.7 FIRE SUPPRESSION SYSTEM 5
/
/*
RE SUPPRESSION WATER SYSTEP
/
LIM ING CONDITION FOR OPERATION
/
/
3.7.7.1 Tne fire scopression water system shall be OPERABLE witt:j TNo OPERASLE fire suporessic.* pumps, one electric moto/ oriven an:
a.
dieselenginecriven,eadhwitnacapacityof25 on withtneirdiscnargealignectotnefiresuppressiop0g:r,
- neacer, t.
I-c seo rate fire water suppi ies,eacnwitnamijdmumcontainecvolume of 328,0C0 galions, ar.:
c.
An OPERASLE low patn cacable of taking suc on from either or both of the fire we*
cistribution p\\er storage tarik(s) and tran(ferring the water through i ing with OPERABLE section/lizing control or isolation valves to the ya hycrant curo valves.jthe last valve anead of the water fle,< alarm avice on ea cn sprinkJer or hose stancoice and the last valve ahead ofhhe deluge valvej n each deiuge or spray system d
recuired to be OPERAB*C per Specifi ations 3.7.7.2 and 3.7.7.5.
APPLICABILITY: At all times.
ACTICN:
a.
With one pump and/or one w te upply inoperable, restore the r
inoperable equipment to ERABL status within 7 days or provide an alternate backup pum or upply The provisions of Specifications 3.0.3 d 3.0. 4 are at applicable.
b.
With the fire suppr ssion wa3er system therwise inoperable, establish a backu fire suppression wateh system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REOUIREMEN
\\
4.7.7.1.1 The [ ire uppression water s ystem shall be dem strated OPERABLE: ~
~
~
At leas once per 7 days by verifying the minimum ntained water a.
i suppl volume.
b.
/st east once per 31 days by starting the electric moto. driven fire s ppression pump and operati.*g it for at least 15 minute At least once per 31 days by verifying that each valve, can 1, power c.
operated or automatic, in the flow path is in its correct pos' tion.
HOPE CREEK 3/4 7-21 APR 1 1 1955
PLANT SYSTEM 5 RVEILLANCE REOUIREMENTS Kbntinued)
\\
\\d At least once per 12 montns cy performance of a system flu
\\
oycyclingeacntestablevalp/
e.
xnt least once cer 12 months e in :ne flow path tnrougn at least one comolete cycle of full Yravel f
At east once per 18 montns by performing a system ' nctional test whictlyincluces simulatec automatic actuation of t system tnrougnout its oce[ating secuence, anc:
f N
/
1.
Verif' ing that each autcmatic valve in the fle. patn actuates to its correct position',
2.
Verifying that each fire suppressiop pump develoos at least 2500 gem a a system hebd of 275 fee.,
3.
Cycling each alve in tne flow p h that is not testable during plant operation through at least one complete cycle o' full travel, and
/
/
4.
Verifying that each ire p6ppression pump starts sequentially to maintain the fire adression water system pressure greater uhr. vi 6 5', u 100 - (.
g.
At least once per 3 year by p\\egforming a flow test of the system in accordance with Chapter 5, Secti 11 of the Fire Protection Handbook, 14th Edition, publish by tie Nat'onal Fire Protection Asscriation.
4.7.7.1.2 The diesel driven ire supp ession p*mp shall be demonstrated OPERASLE:
a.
At least once er 31 days by:
1.
Verify ng the fuel storage tank contain at least 135 gallons of
- ?uel 2.
.arting the diesel'driren pump from ambient onditions and I
operating for greater than or equal to 30 minu~ es.
b.
.A least once per 92 days by verifying that a sample o diesel fuel g
rom the fuel storage tank, obtained in accordance with VSTM-D270-75, is within the acceptable lim its specified in Table 1 of A TM D975-77 when checked for viscosity, water and sediment.
c.
At least once per 18 months by subjecting the diesel to an in 'ection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.
(
HOPE CREEK 3/4 7-22 APR 1 1 1555
!W N\\
PLANT SYSTEMI RVEILLANCE RE0VIREMENTS (Continued) l
/
4.7.7.
3 The diesel driven fire pumo starting 2*-volt battery cank a7:
cnarger hall be cemonstrated OPERABLE:
/
a.
At least once per 7 days by verifying tna.:
1.
Tne electrolyte level of each pilot cell is acov_ tne plates,
/
2.
Th pilot cell soecific gravity, correctec t V77*F and full ele *rolyte level, is gr eater tnan or ec;u o 1.200, anc 3.
Tne ov all battery voltage is greater t an or ecual to 24 volts.
b.
At least once r 92 days by verifying tha the soecific gravity is appropriate for antinued service of tne attery.
c.
At least once per 1 months by verify ~ g tnat:
f 1.
The batteries, ce 1 plates an battery racks snow no visual indication of phys al camag, or acnormal deterioration, and 2.
Battery-to-battery an,.f+minalconnectionsareclean, tight, te g
(
e r, -,.,, 4 ~,
m-a m 4 + s m., + 4,., -, e 4,, - 2.
4 a N
i
.y HOPE CREEK 2/4 7-23
.Ap,e. ;.333
- - - ^ - - - - - ' ~ " ' - - - - ' - ' ^ ^ - ' - - - ' - - ^ - - - - - ' ^ ^ - ^ - - - - - - - - ' ^ ' ^
ll/Sl PLA'iT SYSTE."?
SPRAY AND/OR SPRINKLER SYSTEMI IMITING CONDITION FOR OPERATION s
3.
- 7. 2 Tne following spray ano sprin@ier systems shall be OPERAELE:
l
\\
i SYSTE."
HAZARDARRl ELEVATI0h NL Reactor Euiitin; Motor Contr'b1 Center Area 420; 77' 1951E Corricor 430;N 100' 1P516 FRV5" Recir:. C$arcoal Filter 132' 1PD2 FRV5 Re:irc. Cha'xcoal Filte-130' iPD4 FRV5 Vent Unit Cnhqcoal ilter 145' 1P05 FRV5 Vent Unit Char cal Filter 145' 1P06 FRV5 Recire. Charcoa Filter 15'2' 1PD7 FRV5 Recirc. Charcoal ilter
.52' 1PDS FRV5 Re: ire. Charcoal F1 te-178'E" 19D10 FRV5 Recirc. Charcoal Filta-17S'6" 19011
\\
Auxiliarv Euildino Control and 0/G Areas Cable Screading Roo 77' IP5" Corridor 5207 77' 1PS6 Corricor 5237 77' 1957 Electrical Access 5339 102' 1P58
- Cua Lru) Ewu ip;..eoL Hettam ne 117 T 1D25 Electrical Access 5401 124' 1P59 Elec. Cable Chase 5203, 5323, 53', 540,
77', 102', 124',
1P510 5419, 5531 130', 137, 150' Ele:. Cable Chase 5204, 5324,.332,
- 5406, 77', 102', 124',
1P511 5420, 5532 130', 137, 150' Elec. Cable Cnase 5205, 53^., 5333,
- 5407, 77', 102', 124',
IPS12 5421, 5533 130', 137, 150' Elec. Cable Chase 5206,.326, 5334,
- 5408, 7',
102', 124',
IP513 5422, 5534
'0', 137, 150' Ecergency Charcoal F' ter 15 '
101 Emergency Charcoal ilter 153' 1D2 Diesel Tank Room 07 54'
'1D22 Diesel Tank Roor 5108 54' 1D23 Diesel Tank Ro. 5109 54' 1024 1
Diesel Tank P om 5110 54' 1D25 H and V Cha e 5535 150' 1P514 Auxiliarv"Suf dino Radwaste and Service Areas Electr' al Access Area 3204 77' 1PS6 Elect ical Access Area 3425 124' IP59 Sou
& Central Raosaste & Service Area 137' W56 Inta). Structure ervice Water Pump Room 1P51 Service Water Pump Room IPS2
" Filtration, Recirculation and Ventilation system H3PE CREEK 3/4 7-24 ArR i 1 555
18 'd
/
PLANT SYSTEMI SURVEILLANCE REQUIREMENTS (Continued)
/
ADPL CABILITY:
Wnenever equipment pro tected by tne spray and/or sprinVier syste r is recuired to be OPERABLE.
ACTION:
Wi*n one or more of tne aoovp recuireo spray and/or s;:rinkier systers a.
inoarable,withinonenourpstablisnacontinuousf4rewatenwitr backth. fire suppression equi) ment for tnose areas 'n wnicn recuncant.
systema or comoonents could.)e camaged; for otner areas, establist
~
an houriy fire waten patrol.
b.
Tne provisi ns of Specification 3.0.3 and 3.0.4 are not applicable.
fUfVEILLANCE REOUIREMENTS
)
4.7.7.2 Each of the acove\\
ay and spr/
i quireo sp inkler systems snall ce demonstrated OPERABLE:
L M icen t..w per 31 dhys by ver ying that each valve, manual, power operated or automatic, i the f} w path is in its cor in posidg;t b,
At ieest eats ou 12 a6ainI flow path through at leas %' cc:d mu besn_teg151e salve in the ty i
r.plete cycle cf full travel.
c.
At least once per 18 me ns:
1.
By performing a ystem functi al test which includes simulated automatic actu wion of the syst m, and:
a)
Verify *tig that the automatic lves in the flow path actuate to tb ir correct p asitions on a test signal, and i
b)
Cy ling each valve in the flow pae that is not testable ring plant opera tion through at I st one con.plete cycle of full travel.
2.
E, a visual inspection af the dry pipe spray nd sprinkler headers, xcept for headers loca ted inside charcoal fil r units, to verify their integrity, and By a visual inspection af each sprinkler or deluge ozzle's l
spray area, except for nozzles and perforated pipe 1 ated inside charcoal filter units, to verify that the spray patte is not obstructed.
d.
At least once per 3 years by performing an air flow test throug. each deluge sprinkler header and verifying eact, open head deluge sprin' ler is unobstructed.
HOPE CREEK 3/t 7-25 A.t.. ; ; L2
'\\
RJ??
/
\\
\\
\\
N, PLANT SYSTEMI 0.,
SYSTEM 5 LI.TTING CONDITION FOR OPERATION
\\
3.7.7.
The following low pressure CO systems shall be OPERA 5LE:
2
\\
Hazahd Arez Elevatier Svs em Nc.
Auxiliary EiPlding Control & D/G Areas j/
a.
Fuel Tank Room 511C Sa' IC'.
t.
Fuel Tank ccm 5109 Sa' 100 c.
Fuel Tank Ro'tm 51CE 5*'
103 c.
Fuel Tank Rec.'% 51T Sa'
/
IC' e.
Diesei Generato'r Room 530~.
102' 1C5 f.
Diesel Generator.ccm 530E 100' 1CE g.
Diesel Generator R' ace 5305 10; 1C7 h.
Diesel Generator Roce 530" 1C2' 1CE i.
Control Ecuio. Rocm 62:anine 5447 117'-E" 1CIC Wneneverequ\\imentprotected by Jffe CO., systems is recuire
/
APPLICASILITY:
be OPERAELi.
\\
ACTION:
a.
Witn one or more of the abo e rjrquired CO systems inoperable, 2
within one hour establish a obtinuous fire watch with backup fire l
suppression equipment for trJeh areas in which reduncant systems or components could be dam 'ged; -or other areas, establisn an hourly fire watch patrol.
b.
Tne provisions of Spe fication 3.0.' and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS Each of the ab ve required Cb systems sha(1 be demonstrated 4.7.7.3.1 OPERABLE at least once r31daysbyvefifyingthatechvalve, manual, power operated, or automatic in the flow path is in its corr -t position.
4.7.7.3.2 Each of e above required low pressure CO systtms sh 11 be 2
demonstrated OPE
- LE:
I a.
At 1 est once per 7 days by verifying the C0 storage +ank level to be
.gre ter than 55% and pressure tobegreater$han275ps'g,and b.
least once per 18 conths by verifying:
N 1.
The system, including associated ventilation system fir dampers and fire door release mei:hanisms, actuates, manually and automatically, upon rece ipt of a simulated actuation signa and 2.
Flow frem each accessible nozzle during a " Puff Test."
HOPE CREEK 3/4 7-26 n r n 1,,:,,,..,
2 :ca
/
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. 2/2 i
PLANT SYSTEMI s
HALON SYSTEM I
I LIMITING CONDITION FOR OPERATION
/
\\
/
3.7.7.\\"
The Control Room Console Pit Falon system shall be OPERABLE w'In the storage \\ tanks having at least 95% of fdll enarge level.
N APPLICAEILITY: Wnenever equipment protected by tne Haion system s recuirec to ce OPERAELE
/
/
ACTION-N Witn the Moove recuired Halog system inoperable within one nour a.
establisn h continuous fire Watch witn backco, fire suporession g
ecuipment fo thoseareasinhhichrecuncant ystems or components could be dama d; for other areas, establis an hourly fire watch patroi.
b.
Tne provisions of eecifications 3.0.3 nd 3.0.4 are not apolicable.
SURVEILLANCE REOUIREMENTS
\\\\
l
- 4. 7. 7. 4 The above required Halon s tem all be oemonstrated OPERABLE:
a.
At least once per 6 months b. verifvino Halen storace tank level.
\\
b.
At least once per 18 mont by nerformance of a flow test through s
accessible headers and n.zles t assure no blockage.
4 I
HOPE CREEK 3/4 7-27 AE2 :
if:S
y
\\
c2// 29
\\,
i Ns N
PLANT SYSTEM 5
\\
\\ FIRE HOSE STATIONS IFITING CONDITION FOR OPERATION
/
- 3. 7. iM The fire nnse stations shown in Table 3.7.7.5-1 shall be OPE ELE.
N
- ne areas protected oy tne f'/
APPLICASILITY:
knenever ecuiorent in re nose stations is, recuired to be OPERAELE.
\\
ACTICN:
\\
7
/
a.
Witn 'one or core of the fire nose stations snown % Table 3.7.7.3-;
inoceracie, provice: gatec wye (s) on tne nearest /0PERAELE nose stati on('s).
One outlet of the wye shall ce cor>dected to tne stancarc length of hose provicec at t ie nose station.
the wve shaN be connected tD a length of hps/ine second outlet of e sufficient to provice coverage for 'tne area lef t ulorotected by Jne inoperable hose statier..
Wnere it can b'e cemonstrated that the physical routing of the fire s
nose woulc result.in a recccnizable ha:tre tc operatine tecnnicians, plant equipment, or the hose itself., the fire nose shall ce stored in a roll at the ou let of tie OPERA 31.E nose station.. Signs shall be counted'acove the ated wye (s) td identify tne proper nose to use.
The above ACTION shall\\be ac ocali'shed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the inoper-able fire hose is the p mary mpins of fire suppression; otherwise route the additional hose wi th/n24 hours.
The provisions of Specifica ions 3.0.3 and 3.0.4 are not applicable.
1 c.
N SURVEILLANCE REOUIREMENTS 4.7.7.5 Each of the fire hos stations shown 'n Table 3.7.7.5-1 shall be demonstrated OPERABLE:
a.
At least once pe 31 days by a visual inspection of the fire hose stations acces ble during plant operatio'n to assure all required equipment is t the station, b.
At le3st o e per 18 months by:
\\
~
1.
Vis 1 inspection of the fire hose stationk not accessible
- d. ing plant operation to assure all required equipment is at i
fie station.
2./Removingthehosefori'nspectionandre-racking,and
'1/
Inspecting all gaskets and replacing any degraded gaskets in the couplings.
c.
At least once per 3 years by N
1.
Partially opening each hose station valve to verify valve OPERABILITY and no fic, blockage.
2.
Conducting a hose hycrostatic test at a pressure of 150 psig or at least 50 psig above the caximum fire cain operating pressure, whichever is greater.
ti:PE CREEK 3/a 7-28 APR 1: '955 m -
I
$lkl
.N x
\\
TABLE 3.7.7.5-;
N FIRE HOSE STATIONS s
\\
LOCATION HOSE RACK ELEVATION CO LUM.',
IDENTIFICATICA
\\
/
a.
Reae:.cr Euildin;
\\
Sa ' \\
W-14E 1AHR200 Sa' s
W-23R 1 ERR 200 52'
\\
P-23R ICHR20
\\
5**
P-14R 77' x
W-14R
'/IDHR20:
g 1EHR2CC 77 W-24.2 IFHR200 77-
\\
N-24.2 1GHR20C 77'
\\
V-14R
/
1HHR200 77' R-23R
/
1BHR202 77' V-18.9
/
ICHR200 77 P-18.9
/
10HR202 77' R-14R
/
IEHR202 100'
- -14R 1JHR200 102' Wa24.2 1KHR200 102' N-23R ILHR200 102' Q-15R IMHR200 102' U-14R 1NHR200 10
U-77R IPHR200 100' N-14R /,
1ZHR200 102' Q-21R '
1AHR201 132' U-20R 1QHR200 132' Q-20R 1RHR200 132' R-14R 1YHR200 145' P-17R i
1BHR201 145' U-20R ISHR200 145' Q-15R 1THR200 162'
/
Q-15R f
10HR200 162'
/
U-20R IVHR200 178'
/
Q-ISR 1AHR202 201' h-19R 1CHR201 201' U-20R IVriR200 201' Q-15R 1XHR200 I
b.
Auxiliary / building Control & D/G Areas 54' Vd-29 1AHR4(00 0
54 S-29 1BHR4 54' V-25 ICHR400 54' S-25 1DHR400 54' N-25 1EHR400 77' Vd-29 IFHR401 77' V-25 1GHR400 1
77' N-25 1HHR400 HOPE CREEK 3/4 7-29 A??. ' : 'W
\\
TABLE 3.7.7.541 (Continue:.
/
\\
HOSE RACf.
/
ELEVATION COLUMN IDENTIFICATI0ti Auxiliary Building Control & D/G Areas (continued)
N\\
77' S-25 ILHR400
\\
77' T-29 1PHR40C
\\102' N-25 1AHR40'.
100' V-25 1BHR4T_
102' S-25 10HR401 102' T-30 15HR4:1 102' Vd-23.1 10HR40:
122' x
N-25 1RHR40:
12
R-25 1HHR4:'.
~
130 W-29
~ISHR ::
130' '
T-29 1CHR40; 130' X-25 1GHR4:1 130' U-29 1THR4C.'
137' N
R-24.2 1THR40C 14f'
\\
W-29 IJHR401 14E'
\\
U-25 IUHR4:'.
146
\\ S-29 IVHR40:
150' NX-25 10HR40C 155'-3" N-25 1YHR400 153' V-29 IWHR400 163' T-29 1XHR400 s
163' U-29 \\ '
1KHR401 (s
163' V-26
\\l 1FHR401 178'
~S-29
\\
s-178' V-29
-1RHR401- ---
IQHR401 Auxiliary Building Racwaste & 'Seryicefyreas c.
54' Mc-21.4
\\
1FHR400 Sa' L~-15.8
\\
0AHR300
\\
77'
, Md-21.4 IJHR400
\\
102' Md-21.4 INHR400 102'
/
Mc-19 IPHR400 102'
/
L-15.8 0QHC300 124' L-21.4 OXHC300 124'
/
L-25.9 0ZHC300 124'
/
L-34 OYHC300~
137'
/'
K-19.9 OEHC301 137'
/
'Ha-19.9 FHC301 1
137'
/
K-25.9 0)iHC301.
137' K-25.9 OJHC301 137.'
K-33.1 OLHC301 137'/
Ha-34.6 OKHC301 137' Mc-29 OMHC301 157' K-21.4 OGHC301
~
55' 3" K-25 OSHR301 155'-3" L-25.9 OXHR301
~
153'-6" Md-21.4 10HR201 d.
Intake Structure 100' 1AHR500 100' IBHR500 HOPE CREEK 3/4 7-30 AFR 1 1585
\\
hk
\\
sy PLANT SYSTEM 5
\\
l
\\3/4.7.8 FIRE RATED ASSEMBLIES l
/
LIMITING CONDITION FOR OPERATION
/
/
3.7.8 ' All fire rated assemblies, including walls, floor / ceilings, caMe tra3 enciosures and otner fire carriers, seaarating safety related fire areas or secarating portions of recuncant systems imcortant to safe shutcewrr'within a fire aret, and all sealing devices in fire ratec asseroiy oenetrations, including fire coors, fire wincows, fire camcers, cable, piping anc ventilatic.-
cuct cenetration seais anc ventilation lseais, shall be OPERAELE.
APPLICAEILITY-At all times.
ACTICS-
/'
/
a.
With one or nore of the above recuired fire / rated assemblies and/or sealing cevicessinocerable, within one hour-1.
Verify the OPERASILITY of fire detectors on both sides of the affected penetration and l establish a daily fire watcn patrol, or 2.
Verify the OPERABILITY of firefdetectors on at least one side of the affected penetration and.e'stablish an hourly fire watch patrol, or
/
s
/
s 3.
Establish a continuous' fire watch on at least one side of the A
attectec penetration.
K The provisions of Specific /
b.
ati ons 3.0.3 and 3.0.4 are not applicable.
s SURVEILLANCE REOUIREMENTS
\\
/
I N
4.7.8.1 Each of the above Nequired fire rated asseeblies and penetration sealing devices shall be,v,erified OPERABLE at leastNnce per 18 months by s
performing a visual ins ction of:
a.
_The exoose surfaces of each fire rated assembly.
'N b.
Each fi window, fire damper, and associated harctaa're.
I N
c.
At le st 10 percent of each Sype of sealed penetration.
If apparent thadges in appearance or abnpreal degradations are fo'und, a visual i spection of an additional 10 percent of each type of' sealed enetration shall be made.
This inspection process shall continue s
until a 10 percent sa ple wi;h no apparent changes in appearance or abnornal degradation is found.
Samples shall be selected s6ch that each penetration seal w ill be inspected at least once per\\
15 years.
[
\\
\\
HOPE CREEK 3/4 7-31 A P C. '. 1 ES5' j
N/ bl N
'\\
PLANT SYSTEM ~
N SURVEILLANCE REQUIREMENTS (Continued)
/
/
\\
4.7.8.2 Each of tne aoove recuired fire coors shall be verified OPERASEI Dv insoectipg the closing mechanisms and latcnes at least once oer 6 months, anc cv verife:nc:
/
a.
The OPERABILITY of the fire coor supervision system for/eact elettrically supervised fire hoor by performing a CHANNE.
FUNCTIONAL TEST at least once,per 31 cays.
f N
/
b.
Tnat each locked-closed fire coor is closed at least once oer 7 cays.
N That each unlocked fire coor hithout electrica/
\\
l sucervisicn is c.
closed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
,/
+
c,
//
/
I /
e
\\l/
/\\
\\
\\\\
l
?
""E CREEK 3/? 7-32
\\
e r e.... s h=
\\
kc INSTRUMENTATION BASES
, MONITORING INSTRUMENTATION (Continued) h 3. 7. 8 FIRE DETECTION INSTRUMENTATIO5 bcSILITYofthedetectioninstru.fentationensurestnatbotnaoje te warning capa lity is available for prom::t cetection of fires andy.st fire suppression syst tnatareactuatedD{tdetectionanos' fire detectors, will tscnarge extin-guishing agent in a
~~ely manner.
P rom.,
ression of fires will recuce the potentia or camage to safety relatejdquipment and is an integral element in the overe facility fire protection program.
Fire detectors that are used actua suppression systems represent
- cor; critically impcrtant-ccepen:nt-b.
detectors that are installed solely /c)r ca 4 ant'c # ire protection program t4an-fire warning and notification.
Consequently, the minimum numce f OPERABLE fi detectors must be greater.
The loss of detecti capability for fire suppre
'on systems, actuated by fire detectors, r esents a signifiednt degradation o ire protection for any area.
As a ult, the establishmeni of a fire watch patro must be initi-1erstagethanwouldbewdrrantedforthelosso(fdetectorsthat ated at an e provide y early fire warning. Tne estaalishment of frequent fire b ols in affected areas is required to previce detection capability until t coerable instrumentation is restored to GPERASILITY.
3/4.3.7.9 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowaole out-of-service times and surveillance requirements are consistent with the recom-cendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.10 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION
~
- The radioactive liquid effluent monitoring instrumentation is provided to monitor and contiol, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated and adjusted in I
accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. ~ The OPERABILITY and use of.this instrumentation is consistent with the requirements of General
- Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
(
a H3PE CREEK B 3/4 3-6
'APR 1 1 fc 5
299
{
PLANT SYSTEM ~
BASES 3/4.7.6 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpna emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leaxage from cyprocect, source, and special nuclear material sources will not exceed allowable intake values.
Sealec sources are classified into three groups 'accorcing to their use, witn surveillance recuirements commensurate with the probability of camage to a source in that group.
Those sources which are frecuently handlec are required to be testec more of ten than those which are not.
Sealec sources whicn are continuously enclosed within a shielced mechanism, i.e., sealeo sources within radiation conitoring devices, are consicered to De stored anc nee: not be tested unless tney are removed f ro= the shieldad mechanisr..
[
3/4 7.7 FIRE SUPPRESSION SYSTEM 5 The OPERABILITY of the fire suppression systems ensures that ade:;uate
're ession capability is available to donfine and extinguish fires occur sup ng in any ortion of the facility where safety related equipment is locat The fire supgession system consists of the water system, spray and/or sp/inkler systems, CG syste=s, a Halon system, ar}d fire hose stations.
Thef o11ective capability o he fire suppression systems is adequate to minimi e potential damage to safet elated equipment and i's a major elemert in e facility fire protection program.
In the event that rtions of the tiire suppressic systems are inoperable,~
alternate backup fire figh 'ng equipment is required o be made available in the affected areas until t noperable equipment s restored to service. When the inoperable fire fighting
'pment i s inten d for use as a backup meant of fire suppression, a longer pe ' d of time
- allowed to provide an alternate means of fire fighting than if the
- perable equipment is the primary means of fire suppression.
l The surveillance requirements p ovi kassurancesthattheminimum OPERABILITY requirements of the f. e suppres\\{on systems are met. An allowance is made for ensuring a sufficie volume of Hahq'1 in the Halon storage tanks by verifying the leyel in the tan s.
Leve' measuremants are made by either a U.L.
or F.M. approved method.
In the event the re suppress' ion water system becomes inoperable, I
iernediate correctiv measures must be taken since this sysh m provides the major fire suppression pability of the plant.
3/4.7.8 FIR: RATED ASSEMBLIES Th functional integrity of the fi e barrier penetrations ens'ures that fires ill be confined or adequately re ;arded from spreading to adjacent artions of e facility.
This. design feature mJnimizes the possibility of a singl' fire pidly involving several areas of the facility prior to detection and extin-guishment. The fire barrier penetratio ls are a passive element in the facility fire protection program and are subject to periodic inspections.
HOPE CREEK B 3/4 7-4
'AFE1;'Mr v
m
~.
,v---w
-.-~.,,e, s
,n--.-n--
h0 h i
PLANT SYSTE."'
BASEI 2,
N rIRE RATED ASSEMELIES (Continued)
I
'er penetrations, including cable penetration barrier tre ocors and oaccers nsioered functional ween tne visually observ
<ondition is tnat are not in the as-destcned conditielFor tnose fire baniE~r penetrations tne same as the as-cetignec condition.
4 e
n, an evaluatittfi shall ce performed te snow that tne ecdification nasw \\ grhded the at oe fFe rating of tne fire barrier cenetratier..
During periods of time wnen the rD m are not functional, either, 1) a centinucus fire watch is recuir~ec to be maintailiedQn the vicinity of tne af-fecte: barrier, 2) the, fire oetectors on at least oneMce of the affectec barrier cust be vecified OPERAELE and al hourly fire watenNatrol established until the barcief is restored to functional status, or 3) thebe detectors on both si<res of the affected barrier ebst be verified OPERASLE an'd7 daily fireadiiicn oatrol established until the barrier is restored to functiona' A 1 ut.
3/*.7.9 MAIN TURBINE BYPASS SYSTEv i
Tne main turbine bypass system is required to be OPERABLE consistent with tne assumptiers of the feecwater controller failure analysis for FSAR Chapter 15.
J 4
i I
HCPE CREEK B 3/4 7-5 APR 1 1 tsc5
2W1 6.0 JOMINISTRATIVE CONTROLS 6.1 RESPONSIBILITV 6.1.1 The General Manager - Hope Creek Operations shall be responsible for overall unit operation and shall delegate in writing tne successi,on to this responsibility during his aosenct.
5.1. 2 The Senior Nuclear Shif t Suoervisor or curing his aosence from tne centrol room, a cesignated individual shall be responsible for tne control room command function.
A management directive to this effect, signed oy the Vice Presicent - huclear shall be reissued to all station personnei on an annual basis.
6.2 GRGANIZATIch 0:FSITE 6.2.1 The offsite organization for unit management and technical support shall ce as shown on Figure 6.2.1 ~.
UNIT STA::
6.2.2 Tne unit organization shall be as shown on Figure 6.2.2-1 anc:
Eacn on duty shift shall be composed of at least the minimum shift a.
crew composition shown in Table 6.2.2-1; o
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the control room; A Radiation Protection Technician" shall be on site when fuel is in c.
the reactor; d.
ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concur-rent responsibilities during this operation; eM~
ire brigade of a( least five members shall be m tetneT~on site at al The fire b -igade shall ude the Shift o
Supervisor, the Shift e
~
1
. nor the two other members of the minimum shif er Treces ;De fe shutdown of the unit "and an required for sther essentia ons during a emergency; and "The Raciation Protection Technician be "r: tricce : m::itioni ay be m ~ e e - -
u-
- e rerewa for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in lukAVAubfEl order to accor.::ocate unexpected absence, provided 1mmediate action is taken to fill the required positio HOPE C?.EEx g_
APR2: ;e:S
.