ML18052A607

Forwards Rev 2 to Attachment 1A,to Essential Safe Shutdown Equipment Used for Alternate Shutdown & Attachment a to Rev 7 Index of Fire Protection Exemption Requests & Modified Commitments

ML18052A607
Person / Time
Site:	Palisades
Issue date:	07/21/1986
From:	Berry K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8607250054
Download: ML18052A607 (24)

Text

consumers Power POW ERIN&

NllCHl&AN"S PRO&RESS General Offices:

1945 West Parnall Road. Jackson, Ml 49201 * (517) 788-1636 July 21, I986

Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

FIRE PROTECTION - ESSENTIAL EQUIPMENT FOR ALTERNATE SHUTDOWN Kenneth W Berry Director Nuclear licensing Consumers Power Company originally submitted a list of equipment essential for safe shutdown when using the Alternate Shutdown Method described in Attachment IA to our August IO, I984 submittal.

On June I9, I985, Consumers Power Company added additional equipment to that list and submitted Revision I of Attachment IA.

As a result of conclusions reached during the NRC staff visit

. to Palisades on June 3 and 4, I985 and the completion of additional analysis, Consumers Power Company has determined that operation of a High Pressure Safety Injection (HPSI) pump will maintain subcooling in the PCS without emptying the pressurizer and will add enough boron to the Primary Coolant System to attain the proper shutdown concentration.

That additional inf orma-tion allowed Consumers Power Company, on October 4, I985, to withdraw a request to exempt the Charging Pump Room from certain applicable criteria of IOCFRSO, Appendix R, Sections III.G.2 and III.G.3.

The withdrawal of this exemption request is dependent on final NRC approval of the calculational methods used to determine that operation of the HPSI pump is an acceptable alternative to the charging pumps.

If a fire occurs in the Auxiliary Building 590' elevation corridor fire area (which includes the Charging Pump Room), HPSI pump P-66B could be used to provide adequate makeup for the PCS inventory, maintain proper pressure, and ensure the required shutdown boron concentration is achieved.

This letter transmits Reyision 2 to Attachment IA to the August IO, I984 submittal.

It is entitled "Essential Safe Shutdown Equipment Used for Alternate Shut-down"; and includes reference to HPSI pump P-66B and its associated flowpaths.

Additionally, Revision 2 includes the Diesel Fuel Transfer pump and its associated flowpaths, the battery powered I25VDC system, Component Cooling Water. (CCW) surge tank level indication, Low Pressure Safety Injection (LPSI) flow indication, and Shutdown Cooling System (SDCS) flow indication~

An editorial change has been made to Enclosure 2 to Attachment IA

• OC0786-0III-NL02

. 8607250054 860721 r *1 PDR ADOCK 05000255\\ ;

F PDR

_L

Director, Nuclear Reactor Regulation Palisades Plant Fire Protection - Essential Equipment for Alternate Shutdown July 21, 1986 Attachment A to this letter is Revision 7 of the index of Consumers Power Company Exemption Requests and Modified Commitments.

e~~

Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0786-0lll-NL02 2

FP0685-0001L-NL04 Docket 50-255 ATTACHMENT A TO THE JULY 21, 1986 CONSUMERS POWER COMPANY FIRE PROTECTION SUBMITTAL FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS INDEX FOR ATTACHMENT - REVISION 7 July 21, 1986 3 Pages

FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 7 INDEX FOR ATTACHMENTS NRC APPROVAL ATTACHMENT STATUS 1

N/A Appendix A N/A lA N/A 1B N/A lC N/A 2

N/A 3

Withdrawn 6/19/85 4

Withdrawn 6/19/85 5

Withdrawn Appendix A Of Attach 5 6/19/85 N/A FP0685-0001L-NL04 NEW INFORMATION THIS SUBMITTAL (YES/NO)

NO NO NO NO NO NO NO NO NO NO July 21, 1986 Page 1 of 3 TITLE APPENDIX R REVIEW PROCESS (Original Submittal April 23, 1984 - Rev 1 July 16, 1984 -

Rev 2 August 10, 1984 Rev 3, December 28, 1984)

ILLUSTRATIONS, APPENDIX R REViEW PROCESS of Attach 1 (Original Submittal December 28, 1984)

ESSENTIAL EQUIPMENT FOR SAFE SHUTDOWN POST-FIRE (Original Submittal August 10, 1984 Revision 1 - June 19, 1985)

Revision 2, July 21, 1986 FIRE AREA IDENTIFICATION, AUTOMATIC FIRE SUPPRESSION COVERAGE, AND FIRE DETECTOR COVERAGE (Original Submittal July 16, 1984 - Rev 1 August 10, 1984)

EMERGENCY LIGHTING (Original Submittal, July 16, 1984 Revision 1 - October 1, 1984 Revision 2 - June 1985.)

.MODIFICATIONS TO PREVIOUS FIRE PROTECTION COMMITMENTS (Original Submittal April 23, 1984 - Revision 1 July 16, 1984 Rev 2 August 10, 1984)

I EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 SERVICE WATER PUMP SEPARATION IN INTAKE STRUCTURE (Original Submittal April 23, 1984 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 ENGINEERED SAFEGUARDS AREA (Original Submittal April 23, 1984 - Revision 1 July 16, 1984)

EXEMPTION REQUEST -

SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 RATED BARRIERS (Original Submittal April 23, 1984 - Revision 1 July 16, 1984)*

TEST REPORTS WHICH SUBSTANTIATE ATTACHMENT 5 -

ITEMS a,b,c and d (Original Submittal July 16, 1984)

FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 7 INDEX FOR ATTACHMENTS NRC APPROVAL ATTACHMENT STATUS 6

Withdrawn 6/19/85 7

Withdrawn 10/4/85 8

N/A 9

Approved 7/12/85 10 Approved 7/12/85 11 Approved 2/8/83 12 Withdrawn 4/23/84 13 Denied 2/13/85 FP0685-0001L-NL04 NEW INFORMATION THIS SUBMITTAL YES/NO NO YES NO NO NO NO NO NO July 21, 1986 Page 2 of 3 TITLE EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 COMPONENT COOLING WATER ROOM (Original Submittal April 23, 1984 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.G.2 AND III.G.3 OF APPE~IX R TO 10 CFR 50 - CHARGING PUMPS P-55B AND P-55C (Origi~al Submittal April 23, 1984 - Revision 1 July 16, 1984)

SUMMARY

, PLANT MODIFICATIONS RESULTING FROM "APPENDIX R SELF-AUDIT" (Original Submittal April 23, 1984 - Revision 1 July 16, 1984)

EXEMPTION REQUEST -

SECTION III.G.3 OF APPENDIX R TO 10 CFR 50 ENGINEERED SAFEGUARDS PANEL ROOM (Original Submittal July 25, 1983 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.G.3 OF APPENDIX R TO 10 CFR 50 CORRIDOR BETWEEN CHARGING PUMP ROOM AND SWITCHGEAR ROOM lC (Original Submittal July 25, 1983 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.G.3 OF APPENDIX R TO 10 CFR 50 CONTROL ROOM (Original Submittal July 1, 1982 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.G.l.a OF APPENDIX R TO 10 CFR 50 REPAIR PROCEDURE HOT SHUTDOWN INSTRUMENTATION (Original Submittal December 6, 1982 - Revision 1 July 16, 1984)

EXEMPTION REQUEST - SECTION III.L.4 OF APPENDIX R TO 10 CFR 50 LOCAL TENDING OF EMERGENCY DIESEL GENERATORS (Original Submittal August 10, 1984)

FIRE PROTECTION - EXEMPTION REQUESTS AND MODIFIED COMMITMENTS - REVISION 7 INDEX FOR ATTACHMENTS NRC APPROVAL ATTACHMENT STATUS 14 OPEN 15 Approved Z/23/85 FP0685-0001L-NL04 NEW INFORMATION THIS SUBMITTAL YES/NO YES NO july 21, 1986 Page 3 of 3 TITLE EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 INSTRUMENT SEPARATION INSIDE CONTAINMENT (Original Submittal July 16, 19.84 - Rev 1 December *28, 1984 Rev 2 October 4, 1985)

EXEMPTION REQUEST - SECTION III.G.2 OF APPENDIX R TO 10 CFR 50 CABLE SEPARATION INSIDE CONTAINMENT (Origi.nal Submittal July 20, 1984) e*

FP0786-0111A-NL02 ATTACHMENT lA Consumers Power Company Palisades Plant Docket 50-255 ESSENTIAL SAFE SHUTDOWN EQUIPMENT USED FOR ALTERNATE SHUTDOWN Revision 2 Original Submittal August 10, 1982 Revision 1 - June 19, 1985 Revision 2 - July 21, 1986 3 pages

ATTACHMENT lA ESSENTIAL EQUIPMENT FOR SAFE SHUTDOWN POST-FIRE USING ALTERNATE SHUTDOWN Revision 2 Pages 4 and 5 contain the list of essential equipment for post-fire safe shutdown when the Alternate Shutdown Panel (ASP) is used.

This essential equipment list has been determined using the following scenario and assumptions.

Scenario:

When a fire occurs in one of the four areas requiring use of Alternate Shut-down (Control Room, Cable Spreading Room, Engineered Safeguards Panel Room, and 590' elevation corridor in the Auxiliary Building), it is possible, using the method described herein, to meet the criteria of the appropriate sections of Appendix R.

Concurrent with this fire, outside power (including the electrical grid) is unavailable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

No additional non-fire related accidents ~re postulated to occur at this time.

Requirement:

1.

The plant must be taken to the hot shutdown condition (HSD) and be capable of remaining in that condition for a period as long as conditions require.

2.

No repairs are allowed on equipment necessary to achieve hot shutdown.

3.

The equipment used for the transition to and to maintain the cold shutdown (CSD) condition m~st be operable in time to have the ability to achieve cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of reactor trip:

4.

Repairs *using onsite materials are allowed on equipment necessary to achieve cold shutdown.

Appendix R of 10 CFR 50 states that electrical wiring and cabling to equipment necessary to meet the requirement be in at least two redundant paths; and, those paths must be separated by conditions which meet certain criteria.

Assumptions:

1.

Any electrical wires or cables which are not separated by Appendix R criteria or exemptions thereto can cause an open or a short circuit which results in a spurious actuation that will adversely affect the safe shutdown process.

2.

Any wire can become charged with a voltage which will cause spurious operation of the equipment to which it is attached.

Exception -

1) All three phases of the power supply to a motor will not "hot" short and cause spurious operation, and 2) 125V control wires will not hot short at FP0786-0111A-NL02

ATTACHMENT lA Essential Equip for Safe Shutdown Post-Fire 2

the proper voltage on both the 125V and neutral wires of the same circuit at the same time in order to cause a lack of speed control for the 1-1 emergency diesel generator.

3.

Three phased motorized valves will fail in the "as is" position if the control circuit is not affected.

4.

Passive type equipment is not listed.

Passive equipment is defined as equipment that requires no outside actuation in order to accomplish its purpose, ie, a heat exchanger.

5.

Any location in the plant which contains equipment necessary for post-fire safe shutdown is accessible within one hour of the time a fire is reported.

Method and Theory:

The reactor is tripped and decay heat is removed from the core by natural circulation.

As the primary coolant goes through the Steam Generator it transfers the heat to secondary water.

The secondary water turns to steam, increases secondary system pressure and opens the secondary code safety valves to allow the steam to enter the atmosphere.

Water is supplied to the secon-dary side of the steam generators by the Auxiliary Feedwater (AFW) system.

AFW pump P-8B is driven by Turbine K-8 and is powered by steam from Steam Generator A after it. passes through CV-0522B and PCV-0521A.

CV-0522B is either electro-pnuematically controlled or manually controlled; PCV-0521A maintains turbine inlet pressure by pneumatic balance with line pressure, fails closed, and can be by-passed by operating a manual valve.

Both valves, CV-0522B and PCV~0521A have a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> emergency supply of air (N2).

Flow of water from P-8B to SG-A and SG-B is controlled electro-pnuematically with a hand indicating controller using CV-0749 and CV-072~ or, after disconnecting the air supply and causing CV-0749 and CV-0727 to fail open, manually operat-ing the in-line motor-operated FOGG valves.

(M0-0753, M0-0760, M0-0743, M0-0798)

The PCS stays 25° sub-cooled for 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Ref 1) without the addition of any coolant.

During the 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, local control of the diesel generator is established, a charging pump or High Pressure Safety Injection (HPSI) pump P-66B is started and the charging pump or HPSI pump P-66B to PCS flowpath established.

Use of P-66B may be necessary when the fire is in the 590' elevation corridor.

In order to cool the diesel engine on Emergency Diesel Generator 1-1, a Service Water pump must be started within 30 minutes after starting the diesel.

By manually starting and stopping a charging pump or HPSI pump P-66B at their power supply breaker and regulating the flow of AFW, the critical safety functions (Reference pages 4 and 5 of this analysis) are kept within acceptable parameters.

Indications of Neutron Flux, S.W.

temperature at the entrance and exit of the 1-1 emergency diesel generator cooling system, Charging Pump Flow, Cone. BAT level, PZR1 1, PZR eye p~ess SG-Alevel' SG-B1 el' Condensate Stora~e Tank Level, AFW

~* ow, TH, le* and SG pressure enable ~Ke operator to maintain the hot shutdown condition.

FP0786-0111A-NL02

ATTACHMENT lA Essential Equip for Safe Shutdown Post-Fire 3

Transition to the cold shutdown condition is initiated by manually opening the main steam isolation valve bypass and the flowpath to the high volume air ejector and relief valve RV0634.

A charging pump, being gravity fed by the concentrated boric. acid t.ank or HPSI pump P-66B being gravity fed from the Safety Injection Refueling Water Tank (SIRWT) keeps PCS pressure and level within acceptable limits.

When the PCS is cooled to the 325°, the Shutdown Cooling System, the Component Cooling Water (CCW) System and Service Water (SW) Systems are used to continue the transition to the cold shutdown condition.

Manual Operator Actions There are a number of instances in which redundant valve circuitry is not separated, or does not exist, however, the plant's ability to shut down due to a fire is not endangered because adequate time is available for manual operator actions inside the fire area of concern.

A description of the manual actions which may be required is included in the.March 19, 1985 Consumers Power Company submittal.

References:

1.

Consumers Power Company letter to NRC dated June 4, 1986 (Additional Information - Fire Protection)

FP0786-0111A-NL02

Essential Equipment REACTIVITY Hot

1. Service Water Pump Shutdown

2. Diesel Generator (HSD)

3. 2400 VAC BUS

4. 480 VAC BUS

5. Charging Pump or HPSI Pump

6. Battery Powered 125 VDC RCS PRESSURE

1. Service Water Pump

2. Diesel G~nerator

3. 2400 VAC BUS

4. 480 VAC BUS

5. Charging Pump or HPSI Pump

6. Battery Powered 125 VDC Essential Flowpaths and their included valves - Items No.

FP0786-0111B-NL02 1,

RCS INVENTORY

1. Service Water Pump

2. Diesel Generator

3. 2400.VAC BUS

4. 480 VAC BUS

5. Charging Pump or HPSI Pump

6. Battery Powered 125 VDC RCS HEAT REMOVAL

1. Secondary System Code Safety Valves

2. P-8B 2, 3, 4, 9, 11 and 12 of Enclosure No. 1 ESSENTIAL INDICATORS

l.

TH

,4

2.

T

3. sB Pressur9

4.

PZR Level

5.

PZR Pressure

6.

SG-A Level

7.

SG-B Level

8.

AFW Flow to SG-A

9.

AFW Flow to SG-B

10. AFWP Suction Pressure

11. Neutron Flux Monitor (Source Range)

12. Service Water Temperature Entering&~

Exiting the19' 1-1 DG Heat Exchanger

13. Charging Pump Flow

14. Cone.BAT Level

15. SIRW Tank Level

REACTIVITY Transition 1. SW Pump or Diesel 525°F. to Driven Fire Pump 325°F

2. Diesel Generator

3. 2400 VAC BUS

4. 480 VAC BUS

5. Charging Pump or HPSI Pump

6. 125V DC Battery Power RCS PRESSURE Same as for Reactivity Control RCS INVENTORY Same as for Reactivity Control RCS HEAT REMOVAL

1. Hogger

2. P-8B (Steam Driven AFW Pump)

3. Diesel Driven Fire Pump

4. Instrument Air Supply ESSENTIAL INDICATORS Same as Hot Shutdown Essential Flowpaths and their included valves - Items 1, 2, 3, 4, 5, 8, 9, 9a, 10, 11 12, 14, 15 and 16 of Enclosure No 1.

325°F to and including Cold Shutdown Same Equipment as required for 525°F -

325°F transition, plus

1. LPSI Pump

2. CCW Pump

3. Fuel Oil Transfer Pump Same as Reactivity Same as Reactivity Same as Reactivity TH_ or Tc PZR Level PZR Pressure SW Temp. at entry & exit of Diesel Gen-erator Heat Exchanger CCW Surge Tank Level LPSI Flow SDCS Flow Esse*ntial Flowpaths and their included valves - Items 1, 3, 6, 7, 8, 9a, 13, 14, 15 and 16 of Enclosure No. 1 *

. FP0786-0111B-NL02 5

FP0786-0ll 1C-NL02 ENCLOSURE 1 TO ATTACHMENT lA Consumers Power Company Palisades Plant - Docket 50~255 ESSENTIAL FLOWPATHS FOR SAFE SHUTDOWN POST-FIRE July 21, 1986 9 pages

ENCLOSURE 1 TO ATTACHMENT IA INDEX FOR LIST OF VALVES IN ESSENTIAL FLOWPATHS A = Necessary For Hot Shutdown B = Necessary For Transition From Hot Shutdown to Cold Shutdown C = Necessary for Cold Shutdown Item No Flowpath

1.

Service Water To Diesel Generators Heat Exchangers

2.

Concentrated Boric Acid Tanks To Charging Pumps

3.

Charging Pumps To Primary Coolant System

4.

Auxiliary Feedwater Flow - Condensate Storage Tank to Steam Generators Via P-8B

5.

Diesel Fire Pump To Auxiliary Feedwater Suction (P-8B)

6.

Primary Coolant System To Shutdown Cooling To Primary Coolant System

7.

Service Water To Component Cooling Water Heat Exchangers

8.

Diesel Fuel Tank (T-40) To Fire Pump Diesel Driver (K-10)

9.

Steam Generator E-50A To Auxiliary Feedwater Pump Turbine Driver (K-8) 9a.

Safety Injection And Refueling Water* Tank To Charging Pumps

10.

Steam Generator E-50A To Hogging Air Ejector

11.

HPSI Pump P-66B to PCS

12.

Safety Injection And Refueling Water Tank to HPSI Pump P-66B

13.

Component Cooling Water (CCW) Pumps To Shutdown Heat Exchangers to Component Cooling Heat Exchangers and Return To CCW Pumps

14.

15.

16.

Diesel Fuel Tank T-10 To Diesel Fuel Transfer Pump P-18B Diesel Fuel Transfer Pump P-18B To Fire Pump Diesel Fuel Tank T-40 Diesel Fuel Transfer Pump P-18B To Emergency Diesel Generator Day Tank T-25A FP0786-0111C-NL02 Function A, B, c A, B, A, B, c A, B B,

c c

B, c A, B B, c B

A, B A, B, c

B, C B, C B, C

ENCLOSURE 1 TO ATTACHMENT lA LIST OF VALVES IN ESSENTIAL FLOWPATHS AC = Air to Close ND Normally AO = Air to Open NE Normally LO = Locked Open LC = Locked Closed.

NO Normally Open NC = Normally Closed ELC = Electrically Locked Closed ELO = Electrically Locked Open De-energized Energized Manual Over-Ride Capability = A valve that has a handwheel to manually operate the valve.

Fail Open = Valve opens upon a loss of air.

Fail Close = Valve closes upon a loss of air.

Fail As Is = Valve fails as is upon a loss of air.

1.

Service Water To Diesel Generators Heat Exchangers:

16"-428-102SW l 6"-428-103SW 16"-428-104SW CV1319 CV1318 CV1359 CV0845 CV0844

• CV0846 CV0857 CV0876 CV0877 CV0885 CV0884 6"-MV-279-SWS 6"-29-132SW FP0786-0111C-NL02 Service Water Pump P-7A Service Water Pump P-7B Service Water Pump P-7C LO LO LO Crossover Valves Between AC Service Water Pumps AC Non-Critical Service Water NO Shutoff Header A AC Header B AC Crossover Between Service AC Water Headers AC Header A AC Header B AC Header A (To Diesel Generator K-6B)

Header B (To Diesel Generator K-6B)

Header A (From Diesel Generator K-6B)

Header A (From Diesel Generator K-6B)

AC AC NO LO NO NO AO NO NO NO NO NO NO Manual Manual Manual Fail Open Fail Open Fail Close Fail Open Fail Open Fail Open Fail Open Fail Open Fail Open Fail Open Fail Open Manual Manual 2

ENCLOSURE 1 TO ATTACHMENT lA 6"-29-131S'W 6"-MV-278-S'WS Header B (From Diesel Generator K-6A)

Header B (From Diesel Generator K-6A)

LO NO

2.

Boric Acid Tanks To Charging Pumps:

M02170 M02169 3"-N29M2DR-2089 3"-N29M2DR-2095 3"-N29M2DR-2101 Tank T-53B Tank T-53A To Charging Pump P-55A To Charging Pump P-55B To Charging Pump P-55C NC NC LO LO LO

3.

Charging Pumps To Primary Coolant System:

2"-N7M3-2094 l~"-N7M3-2100 li"-N7M3-2106 2"-N7M3-2195 2"-108 CV2111 CV2113 CV2115 M03072 Charging Pump P-55A Charging Pump P-55B Charging Pump P-55C Charging Pump P-55C Charging Pumps P-55B&C To Regenerative Heat Exchangers E-56 To Charging Line Loop lA To Charging Line Loop 2A LO LO LO LO LO NO NO NO RPS! Train 2 SI Tan~ Test NC Line To Charging Pumps AC AC AC 3

Manual Manual Manual Over-Ride Capability Manual Over-Ride Capability Manual Manual Manual Manual Manual Manual Manual Manual Fail Open, Also Manual Over-Ride Capability Fail Open, Also Manual Over-Ride Capability Fail Open, Also Manual Over-Ride Capability Manual Over-Ride Capability

4.

Auxiliary Feedwater Flow - Condensate Storage Tank To Steam Generators Via P-8B:

6"MV-133F'W 6"MV-270F'W 6

11-2 9-0 7 71-F'W 6"-MV-271-F'WS FP0786-0111C-NL02 Redundant To 6"MV-133F'W LO LO LO Redundant To 6"-29-0771-F'W *Lo Manual Manual Manual Manual

ENCLOSURE 1 TO ATTACHMENT IA o"-29-132-FW 6"-14-0742FW CV0727 M00743 M00798 CV0749 M00753 M00760

5.

Diesel Fire Pump 10"-700 FPS 12"-42-114FP 4"-29-0775FW 4"-29-0774FW 6"-29-132FW LO LO To Steam Generator E-50B NC To E-50B NO To E-50B NO To Steam Generator E-50A NC To E-50A NO To E-50A NO To Auxiliary Feedwater Suction From Diesel Fire Pump P~41 LO LO LC LC To Auxiliary Feedwater LO Pump P-8B,

4 Manual Manual AC Fail Open Manual Over-Ride Capability Manual Over-Ride Capability AC Fail Open Manual Over-Ride Capability Manual Over-Ride Capability (P....:8B):

Manual Manual Manual Manual Manual

6.

Primary Coolant System To Shutdown Cooling To Primary Coolant System:

M03015 ELC Manual Over-Ride Capability M03016 ELC Manual Over-Ride Capability M03190 To LPSI Pump P-67B NC Manual Over-Ride Capabiiity 10"-N26M3DR-From LPSI Pump P-67B LO Manual 3193 M03199 To LPSI Pump P-67A LC Manual Over-Ride Capability l0"-N26M3DR-From LPSI Pump P-67A LO Manual 3202 FP0786-0111C-NL02

ENCLOSURE 1 TO ATTACHMENT lA CV3055 CV3212 CV3213 CV3223 CV3224 CV3025 M03008 M03010 M03012 M03014 CV3006 CV3001 CV3002 To Shutdown Cooling Heat Exchangers To E-60B From E-60B To E-60A From E-60A To PCS Loop lA To PCS Loop lB To PCS Loop 2A To PCS Loop 2B To Low Pressure Safety Injection To Containment Spray To Containment Spray

7.

Service Water To CCW And Return:

CV0879 CV0949 CV0913 ELC ELO ELO ELO ELO ELC AO NC NC NC NC ELO AC NC AC NC AC AO NC AC NO AC NC CV0937 To Shutdown Cooling NC AC Heat Exchangers E-60A & B CV0938 Redundant To CV0937 NC AC 12"-428F-101CC To E-60A LO 12"-428F-102CC To E-60B LO 12"-C428F-103CC From E.::.60A LO FP0786-0111C-NL02 5

Fail As Is Fail As Is Fail As Is Fail As Is Fail As Is Manual Over-Ride Capabi~ity Manual Over-Ride Capability Manual Over-Ride Capability Manual Over-Ride Capability Manual Over-Ride Capability Fail Open, Manual Over-Ride Capa-bility Fail Open Fail Open Fail Close Fail Open Fail Open Fail Open Fail Open Manual Manual Manual

ENCLOSURE 1 TO ATTAl:HMENT lA 12"-C428F-104CC From E-60B CV0951 CV0950 LO AO AC 6

Manual NC Fail Close NC Fail Open

8.

Diesel Fuel Day Tank (T-40) To Fire Pump Diesel Driver (K-10):

707-FOS LO

.Manual 1"-703FOS LO Manual

9.

Steam Generator E-50A To Auxiliary Feedwater Pump Turbine Driver (K-8):

4"-153MS 4"-153AMS CV0522B PCV0521A 150FW Controls Inlet Pressure For*K-8 Bypass For PCV0521A NO Manual NO Manual NC AO Manual Over-Ride Capability NC NC Manual 9a.

Safety Injection And Refueling Water Tank To Charging Pumps 3"-N29M2DR-3242

- M02160

• 3"-N29M2DR-2089 To Charging Pump PSSA 3"-N29M2DR-2095 To Charging Pump PSSB 3"-N29M2DR-2101 To Charging Pump P55C

10.

Steam Generator E-50A To Hogging Air Ejector:

CV0510 M0510 6"-14-lOOAE CV0633 CV0634 FP0786-0111C-NL02 Redundant To CV0510 Redundant To CV0633 LO NC LO LO LO NO.

NC NO AC AC NO NO Manual Manual Over-Ride Capability Manual Manual Manual Manual Over-Ride Capability Manual Fail Open Fail Open

ENCLOSURE 1 TO 7

ATTACHMENT lA

11.

HPSI Pump P-66B to PCS 3"-N10M3DR-3178 From HPSI Pump P-66B LO Manual 2"-NllOM3-3179 P-66B Recirculation LO Manual CV-3059 ELO AC Fail Open.

CV-3018 To HPSI Train 2 ELC AO Fail Close CV-3037 From HPSI Pump P-66A ELC AO Fail Close M0-3083 Bypass to Hot Leg NC Fail As Is 3007ES To PCS Loop lA NO Manual M0-3007 To PCS Loop lA LO Manual Over-Ride Capability 3009ES To PCS Loop 1B NO Manual M0-3009 To PCS Loop 1B NC Manual Over-Ride Capability 3011ES To PCS Loop 2A NO Manual M0-3011 To PCS Loop 2A NC Manual Over-Ride Capability 3013ES To PCS Loop 2B NO Manual M0-3013 To PCS Loop 2B NC Manual Over-Ride Capability

12.

Safety Injection and Refueling Water (SIRW) Tank to HPSI Pump P-66B CV-3031 From SIRW Tank NO Fail As Is 6"-N26M3DR-3175 To P-66B LO Manual M0-3190 To P-67B from Shutdown NC Manual Over-Cooling Ride Capability

13.

Component Cooling Water (CCW) Pumps to Shutdown Heat Exchangers to Component Cooling Heat Exchangers and Return to CCW Pumps 16"-428-0940CC P-52A Discharge LO Manual 16"-428-094~CC P-52B Discharge LO Manual 16"-428-0945CC P-52C Discharge LO Manual FP0786-0111C-NL02

ENCLOSURE 1 TO ATTACHMENT lA CV-0946 CV-0945 From Common Discharge Header to CCW Heat Exchanger E-54B From Common Discharge Header to CCW Heat Exchanger E-54A NO NO 16"-428F-0916CC E-54B Outlet LO 16"-428F-0914CC E-54A Outlet LO 10"-29-712CC To Letdown Heat Exchanger LO CV-0910 To Letdown Heat Exchanger AC.

CV-0944A To Spent Fuel Pool Cooling Ab System CV-0937 To Shutdown Heat Exchangers NC CV-0938 Parallel to CV-0937 12"-428F-102CC To Shutdown Cooling He.at Exchanger E-60B 12"-428F-101CC To Shutdown Cooling Heat Exchanger E-60A 12"-C428F-103CC E-60B Outlet 12"-C428F-104CC E-60A Outlet 184CC From Spent Fuel Pool Cooling 20"-428-0919CC P-52A Suction 20"-428-0920CC P-52B Suction 20"-428-0921CC P-52C Suction NC LO LO NO NO LO LO LO AC AC NO NC AC AC

14.

Diesel Fuel Tank T-10 to Diesel Fuel Transfer Pump P-18B 2"-019-103FOS From T-10 to P-18B LO FP0786-0lllC-NL02 8

Fail Open.

Fail Open Manual Manual Manual Fail Open Fail Close Fail Open Fail Open Manual Manual Manual Manual Manual Manual Manual Manual Manual

ENCLOSURE 1 TO ATTACHMENT lA 9

15.

Diesel Fuel Transfer Pump P-18B to Fire Pump Diesel Fuel Day Tank T-40 2"-109-104FO P-18B Discharge 705-FOS NO SV-5353 NC 2"-704-FOS NO LO ND Manual Manual Fail Close on Loss of Power Manual

16.

Diesel Fuel Transfer Pump P-18B to Emergency Diesel Generator Day Tank T-25A 2"-109-104FO P-18B Discharge LO Manual 2"-019-129DE Common Header LO Manual l"-019-127DE To T-25A LO Manual SV-1415 To T-25A NC ND Fail Close FP0786-0111C-NL02

. FP0786-0111D-NL02 ENCLOSURE 2 TO ATTACHMENT lA Consumers Power Company Palisades Plant - Docket 50~255 ESSENTIAL SAFE SHUTDOWN EQUIPMENT USED FOR ALTERNATE SHUTDOWN CALCULATION OF SUBCOOLED PCS DURATION REVISION 2 July 21, 1986 1 Page

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ENCLOSURE 2 TO ATTACHMENT lA ESSENTIAL EQUIPMENT FOR SAFE SHUTDOWN POST-FIRE This enclosure summarizes an analysis which determines the limiting time for initiating charging to maintain PCS pressure and inventory in an appropriate operating range.

Calculation assumptions are summarized below.

With no AC power available the flow in the PCS will be by natural circulation.

No pressurizer heaters are available to control pressure and charging is not available. to provide make up.

Heat removal will be via the steam generators.

Previous calculations have determined that adequate steam removal from the steam generators will be available even without AC power.

Assuming that the reactor is maintained at hot standby, the PCS pressure will decay due to ambient heat losses through the Pressurizer and also coolant leakage out of the PCS.

The PCS pressure decay was calculated using the RETRAN computer code.

Three cases were calculated.

All three cases assumed an initial pressure of 1760 psia (2010 psia less 250 psia drop following trip (1)).

The three cases differed in the assumed PCS leakage:

Case 1 - 15 gpm water leak Case 2 - 14 gpm water leak, 1 gpm steam leak Case 3 - 10 gpm water leak, 1 gpm steam leak The Palisades Technical Specifications allow 1 gpm unidentified leakage from the PCS and 10 gpm total leakage (sec 3.1.5).

Also, the PCS flow through the PCP seals is a total of 4 gpm.

This flow is to the Volume Control Tank.

With no charging, this is the same as a leak from the PCS.

Thus, the maximum allowed loss from the PCS is be 14 gpm.

Case 1 above assumed that the total 15 gpm*leakage is water leakage; whereas, Case 2 assumed that 1 gpm is steam leakage (safety valve leakage).

Case 3 is the same as Case 2 except the PCP seal *leakage was assumed isolated.

Assuming that T hot for natural circulation is 560 degrees (1) the PCS will be 25 degrees subcooled when the pressure is 1378 psia (saturation pressure for 560 + 25 = 585 degrees) *. Thus, the time to reach the 25 degrees subcooling is:

Case 1 Case 2 Case 3 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2.45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> 2.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Case 2 above was recalculated by explicitly modeling ambient heat losses from the pressurizer.

This resulted in a minimum time of 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before calculated PCS subcooling was less than 25°F.

The June 4, 1985 Consumers Power submittal, which supplies additional information, completely describes this new calculation.

FP0786-0111D-NL02