ML20205S820
| ML20205S820 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/08/1988 |
| From: | Bishop E CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205K904 | List:
|
| References | |
| EOP-01-EPP-1P, EOP-1-EPP-1P, NUDOCS 8811110185 | |
| Download: ML20205S820 (14) | |
Text
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F' -w+. ,p CAROLINA POWER & LIGHT COMPANY t
BRUNSWICK $ TEAM ELECTRIC PLANT
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END PATH PROCEDURE: IP 1
D4ERGENCY CPERATING PROCEDURE: E0P-01-EPP-1P VOLUME VI ,
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- {4 Approved By: 6.- 1 AO Date Y General i Manager / Q l '
Manager - Operations Page 1 of 13 0811110105gjoO ppg24 PDR ADOCK
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LIST OF EFFECTIVE PAGES E0P-01-EPP-1P Page (s) Revision 1-2 6 3 4 4 4 5 5 6 6 4 7-9 6 10-11 4 12-13 6 i
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r BSEP/Vol. VI/EOP-01-EPP-1P Page 2 of 13 Rev. 6
A. TITLE - End Path Procedure IP B. ENTRY CONDITIONS
- 1. All control rods did NOT fully insert following a scram AND
- 2. Sufficient boron has been injected to maintain the reactor in hot shutdown C. OPERATOR ACTIONS CAUTION DO NOT SECURE or PLACE an ECCS or RCIC in manual mode UNLESS, by at least two independent indications:
- 1. Misoperation in the automatic mode is confirmed, OR
- 2. Adequate core cooling is assured.
IF an ECCS or RCIC is placed in the manual mode, it will NOT initiate automa-tically. Make frequent checks of the initiating or controlling parameter, b' HEN manual operation is no longer required, RESTORE the system to automatic /
standby mode if possible.
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- 1. RESTORE and MAINTAIN reactor vessel level between +170 and
+200 inches. USE one or eorc of the following systems in an order that will minimize high conductivity feed to the reactor:
RPV Pressure Range System for System Operation
- a. Condensate - - - - - - - - - - - - - - - - - - 200 - O psig
- b. CorAensate/ Booster - - - - - - - - - - - - - - 350 - O psig
- c. Feed Pumps - - - - - - - - - - - - - - - - - 1250 - O psig
- d. CRD --------------------- 1490 - O psig
- e. RCIC - - - - - - - - - - - - - - - - - - - - - 1190 - 62 psig
- f. HPCI - - - - - - - - - - - - - - - - - - - - - 1280 - 120 psig
- g. RHR --------------------- 200 - O psig
- h. Core Spray - - - - - - - - - - - - - - - - - - 300 - O psig BSEP/Vol. VI/EOP-01-EPP-IP Page 1 of 13 Rev. 4
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- 2. IF the CRD Drive Water Pressure Control Valve, C11(C12)-F003 - and tee in-service CRD Flow Control Valve, C11(C12)-F002A(F0028), have been opened to maintain reactor vessel level AND the CRD System is no longer needed to maintain reactor vessel level, THEN PERFORM the following steps to restore the CRD System to normal operation:
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- a. ' SET the setpoint tape on CRDHS Remote Flow Controller, C11(C12)-FC-R600, to 100 gpm.
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- b. SHIFT the CRDHS Remote Flow Controller, C11(C12)-FC-R600, to the "AUT0" position.
/ d. OPEN and LOCK OPEN CRD Pump Condensate Return Isolation Valve.
Ind. Var. COR-V1 (located at CST).
/ e. IF Charging Vater Header Throttle Valve, C11(C12)-F034, was Ind. Ver. manipulated to maximize CRD flow. THEN CLOSE and IMMEDIATELY REOPEN 8) turns Charging Water Header Throttle Valve, C11(C12)-F034
- f. SET the setpoint tape on CRDHS Remote Flow Controller, i C11(C12)-FC-R600, to between 30 and 80 gpm.
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- g. ESTABLISH a drive water header differential pressure between
- 260 and 275 psid, as read on C11(C12)-PDI-R602 on RTGB Panel
! P603, by throttling closed Drive Water Pressure Control Valve.
l C11(C12)-F003.
/ h. IF CRD Pumps Suction Filters Bypass Valve, CO-V306, is open.
Ind. Ver. THEN VERIFY a CRD pump suction filter is in service and CLOSE the CRD Pumps Suction Filters Bypass Valve, CO-V306.
- i. IF both CRD pump suction filters are in service, THEN ISOLATE
, and REPLACE the filter which has the highest dP.
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- j. IF both CRD drive water filters are in service, THEN ISOLATE
! and REPLACE the filter which has the highest dP.
IF while executing this procedure, reactor power is above 3%, THEN 3.
EXIT this End Path Procedure and ENTER the "Level / Power Control" flow path.
- 4. IF, while ex,*cuting this procedure, reactor vessel level CANNOT be determined OR reactor vessel flooding is required, THEN EXIT this End Path Procedure and ENTER the "Flooding Procedure" in the
- Contingency section of this End Path Manual.
- 5. IF reacto vessel level CANNOT be maintained above +170 inches THEN MAINTAIN reactor vessel level above 0 inches.
BSEP/Vol. VI/EOP-01-EPP-1P Page 4 of 13 Rev. 5 I
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- 6. If reactor vessel level CANNOT be maintained above 0 inenes, THEN EXIT this End Path Procedure and ENTER the "Level Restora'. ion Procedure" in the Contingency section of this End Path Manual.
- 7. IF, while executing this procedure, reactor depressurization is Equired, THEN PERFORM the following steps:
- a. IF all control rods are NOT fully inserted, THEN EXIT this End
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Eth Procedure and ENTER the "Level / Power Control" flow path,
- b. IP all control rods are fully inserted. THEN DEPRESSURIZE the
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Eactor per the following steps:
CAUTION g NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running and available for injection.
(1) IF the MSIVs are open, THEN RAPIDLY DEPRESSURIZE the reactor with the bypass valve opening jack.
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(2) IF the reactor CANNOT be depressurized to the main Endenser, THEN manually OPEN all ADS valves.
(a) IF any ADS valve CANNOT be opened, THEN OPEN SRVs UNTIL seven valves are open.
(b) E less than three SRVs are open AND reactor pressure is greater than 50 psig above suppression chamber pressure, THEN ENTER the "Emergency Depressurization Procedure" in the Contingency section of this End Path Manual, and EXECUTE it concurrently with this procedure.
(c) CGNTINUE in this procedure at Step 10.
- 8. IF the MSIVs are open, THEN MAINTAIN reactor pressure below 1025 psig with the bypass valve opening jack or EHC pressure setpoint.
CAUTION
@ NOT DEPRESSURIZE below 120 psig WLESS motor-driven pumps suf ficient to maintain reactor vessel levM are running and available for injection.
- =************************************************** l IF reactor pressure CANNOT be maintained with the EHC System AND j 9.
continuous pneumatic supply is available to the SRVs, THEN OPEN SRVs as necessary to maintain reactor pressure below 1025 psig. USE I
- opening saquence B. F. E, G A, C, J. H. D.
BSEP/Vol. VI/EOP-01-EPP-1P Page 5 of 13 Rev. 6
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1 CAUTION MINIMIZE operations which could dilute boron concentration or spread boron to other support systems. ,
DO NOT COMMENCE a reactor cooldown UNTIL all control rods are fully inserted DR E6RC samples indicate a boron concentration of at least 600 p pm . i T***********************************************************.4****************
- 10. CONTINUE boron injection UNTIL: '
- a. All control rods are fully inserted OR
- c. At least 5030 pounds of borax has been injected.
- 11. VMEN boron injectica is terminated, THEN NOTIFY E&RC to sample reactor coolant fer boron concentration and to refill the SLC tank.
(OP-05)
- 12. IF, while executing this procedure:
- a. -The main condenser is available as a heat sink AND
- c. There has been no indication of a steam line break,
- d. THEN REESTABLISH the main condenser os a heat sink (OP-25). .
CAUTION IF fuel failure is suspected, DO NOT REJECT RWCU to hatwell.
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- 13. IF SJAE, stack, or MSL rediation monitors indiente fuel failure, IHEN PERFORM the following stepst
- 2. NOTIFY E&RC to sample coolant.
- b. MONITOR ARMS. stack, and ventilation radiation monitors.
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- d. PLACE the following valve control switches to "CLOSE "
__ (1) DW FLOOR DRAIN INBD ISOL VLV G16-F003
,_ (2) DW FLOOR DRAIN OTBD ISOL VLV G16-F004 BSEP/Vol. VI/EOP-01-EPP-!P Page 6 of 13 Rev. 4 I
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(3) DW EQUIP DRAIN INBD ISOL VLV, G16-F019 i (4) DW EQUIP DRAIN OTBD ISOL VLV, G16-F020
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- e. NOTIFY Radvaste to place the Reactor Building equipment drain tank pumps into the recirculation mode.
- f. DO NOT OPERATE the mechanical vacuum pumps.
- 14. IF condensate booster pump suction conductivity is greater than 0.3 umho, THEN PERFORM the following steps:
- a. REMOVE affected waterboxes from service.
- b. REALIGN CFDs and CDDs to provide better ion removal.
- c. IF the Condensate /Feedwater System is NOT required to maintain reactor vessel level, THEN PLACE the Condensate System in long cycle cleanup.
CAUTION DO NOT DISPATCH personnel to an area of a suspected break without consideration of adverse environments. _ _. r
- 4**********************************************************
- 15. IF a break outside primary containment is suspected, THEN PERFORM the following steps:
- a. ISOLATE the break by remote or manual operation of the affected valvcs.
- b. REFER to AOP-01.1.
- 16. NOTIFY the SOS to perform the following steps: l
- a. CONSULT PEP Section 2.1.
- b. NOTIFY on-call CP&L supervisor.
- c. NOTIFY NRC per RCI-06.5.
- d. NOTIFY E&RC to sample coolant-
- e. IMPLEMENT OI-22.
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- 17. IF RWCU operation is required to maintain reactor vessel level below
+200 inches, AND all control rods are fully inserted, THEN PERFORM the following steps:
- a. REDUCE CRD flow to 30 gpm.
- b. NOTIFY Radwaste that borated water will be rejected.
BSEP/Vol. VI/EOP-01-EPP-1P Page 7 of 13 Rev. 6 l
CAUTION The water in the reactor recirculation loop is potentially NOT borated. USE caution when starting reactor recirculation pumps to prevent rapid power excursions.
- fe**************************************************************************
- 18. IF the reactor recirculation pumps have tripped, THEN RESTART the reactor recirculation pumps (OP-02).
- 19. CONTINUE performing Containment Control, Local Emergency, and System Recovery Procedures UNTIL the exit conditions for the affected procedures are met.
- 21. SECURE any reactor feed pump that is NOT in service (OP-32).
- 22. WHEN systems that require independent verification for return to service are shut down, THEN PLACE the systems in standby readiness per their respective ops. (Refer to Table 11.7.1 in Volume I, Book 1-AP.)
CAUTION MONITOR reactor power during cool down to prevent inadvertent criticality.
- 23. WHEN E&RC samples indicate boron concentration is greater than 600 ppm OR all control rods are fully inserted, THEN REDUCE reactor pressure and ESTABLISH a cool down rate not to exceed 100'F/hr as follows:
- a. IF the MSIVs are open. THEN REDUCE reactor pressure with the bypass valve opening jack.
- b. IF the MSIVs are NOT open, THEN REDUCE reactor pressure and ESTABLISH cool down rate with one or more of the following systems
,_, (3) Main Steam Line Drains (OP-25)
__, (4) SRVs ,Il[ continuous SRV pneumatic supply is or becomes unavailable THEN depressurize with sustained SRV opening.
BSEP/Vol. VI/EOP-01-EPP-1P Page 8 of 13 Rev. 6 l
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24 kECORD reactor vessel shell temperature, reactor vessel pressure, and recirculation loop temperature -<ery 30 minutes.
- 25. IF the MSIVs are NOT open, THEN CONTINUE in this procedure at ,
Step 30.
- 26. WHEN reactor pressure is approximat ely 850 psig, THEN PLACE the I SULCV in service (OP-32).
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- 27. WHEN reactor pressure e reases to less than 500 psig, THEN P1 ACE the four low condenser vacuum bypass swi'eches to "BYPASS."
- 28. WHEN reactor pressure is approximately 350 psig, THEN MAINTAIN reacter Fe:11 level with one condensate and one condensate booster pump anc SE.L ikE the operating feed pump (OP-32).
29.
Prior to 1 ,), .osig, START a mechanical vacuum pump and SECURE the SJAE (OP-30
- 30. WFEN reactor pressure is less than 125 psig, THEN a method of-r3,tdown cooling should be established as follows:
- a. IF all euntrol rods are fully inserted. THEN shutdown cooling may be established per OP-17 011 Step 31 of this procedure at the SOS's discretion (IF OP-17 is used, THEN caution should be used to prevent spreading boron to other support systems).
- b. IF shutdown cooling with the RHR system cannot be established.
THEN ENTER AOP-15.0 ( Alternate Shutdown Cooling Methods) and ;
CONTINUE in this procedure at Step 38.
NOTE WHEN reactor pressure is less than 125 psig, THEN l the RHR System may be placed in shutdown cooling. ,
However, it is desirable to continue cool down using !
bypass valves. Shutdown cooling should be placed in service when a cool down rate of 2 50*F/hr can no longer be maintained.
- 31. WHEN reactor pressure is less than 125 psig, THEN, COMMENCE shutdown cooling as follows:
BSEP/Vol. VI/EOP-01-EPP-1P Page 9 of 13 Rev. 6 l
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CAUTION WHEN reactor recirculation loop temperature decreases to less'than 300'F, [
cool down rate must be limited to 50*F/hr.
l MINIMIZE operations which have the potential to dilute boron in reactor l coolant.
Service Water Radiation Monitor 2-SV-RX-58 should be in service when F.HR is in shutdown cooling. I
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IF one reactor recirculation loop is isolated, DO~ ~~NOT USE that loop for I IUIR/SDC. l
- ename***
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- a. IF the Reactor Building is accessible, THEN FILL and VENT the IUIR System (OP-17). E
- b. PRESSURIZE the RHR loop A (B) piping as follows:
i _ (1) CLOSE RHR Pump A (B) & C (D) Suppression Pool Suction valve, Ell-F020A (B). ;
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(2) CLOSE RHR Pump A (B) Suppression Pool Suction Valve, Ell-F004A (B). '
4 i (3) CLOSE RRR Pump C (D) Suppression Pool Suction Valve, Ell-F00,C (D). (
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~~ (4) OPEN RHR Pump A (B) Shutdown Cooling Suction t Valve. EIl-F006A (B). j
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(5) OPEN RHR Punp C (D) Shutdown Cooling Suction i Valve, Ell-F006C (D).
r (6) CLOSE RHR HX A (B) Outlet Valve, Ell-F003A (B).
_ (7) CLOSE RHR HX A (B) Inlet Valve. Ell-F047A (B).
i (8) CLOSE LPCI Outboard Injection Valve, Ell-F017A (B).
(9) OPEN LPCI Inboard Injection Valve, Ell-F015A (B). ,
(10) OPEN RHR HX A (B) Bypass Valve, Ell-F048A (B).
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(11) Unit 1 only - OPEN Shutdown Cooling Outboard Suction 1 Isolation Valve, Ell-F008. I (12) Unit 2 only - OPFN Shutdown Cooling Inboard Suction Throttle Valve Ell-F009. '
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BSEP/Vol. VI/EOP-01-tPP-lP Page 10 of 13 Rev. 4 I i t
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- c. VERIFY Minimum Flow Bypass Valve, E11-F007A (B), is closed, THEN OPEN motor breaker for E11-F007A (B).
- d. IF while executing the following step, reactor vessel level decreases by a margin greater than 10 inches, THEN CLOSE Shutdown Cooling Outboard Suction Isolation Valve, E11-F008, OR Shutdown Cooling Inboard Suetion Throttle Valve. E11-F009.
CAUTION The water in the RHR loop is potentially NOT borated. USE caution when ,
starting RHR pumps to prevent rapid power excursions.
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- e. Unit 1 only - THROTTLE OPEN Shutdown Cooling Inboard Suction Throttle Valve, E11-F009.
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- f. Unit 2 only - THROTTLE OPEN Shutdown Cooling Outboard Suction Isolation Valve, E11-F008.
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- g. CLOSE RHR Pump A (B) Shutdown Cooling Suction Valve E11-F006A (B),
OR RRR Pump C (D) Shutdown Cooling Suction Valve, E11-F006C (D),
Tor the RHR pump which will NOT be used for shutdown cooling.
CAUTION DO NOT OPERATE an RHR pump at less than 500 gpm for greater than one minute.
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- h. START the RHR pump that is to be used for shutdown cooling. !
- i. SLOVLY THROTTLE OPEN LPCI Outboard Injection Valve, E11-F017A (B), L to establish 1000 gpm flov.
- j. MAINTAIN approximately 1000 gpm flow for 15 minutes to slowly flush and warm the shutdown cooling loop, INEN ADJUST flow rate to greater than 6000 gpm and less than 770n gpm.
- k. OPEN RHR RX A (B) Inlet Valve, E11-F047A (B) .
- m. CONTROL cool down rate by throttling RRR HX A (B) Bypass Valve E11-F048A (B), and/or RHR HX A (B) Outlet Valve E11-F003A (B).
__ 32. SECURE condenser vacuum (OP-30).
BSEP/Vol. VI/EOP-01-EPP-1P Page 11 of 13 Rev. 4 i
CAUTION WHEN reactor coolent temperature is less than 212*F, coolant must be force-circulated thro 9gh the core in order to monitor coolant temperature.
WHEN reactor coolant temperature is less than 212*F, one method of shutdown cooling CANNOT be secured UNTIL another method is available OR the necessary technical specification requirements that allow operation in the hot shutdown mode are established.
The reactor vessel head bolting studs should NOT be under tension UNLESS the temperature of the vessel head flange AND the head is greater than 70'F.
- 33. WHEN reactor recirculation loop temperature decreases to less than 212*F, THEN OPEN the following valves:
- a. Inboard F.eactor Head Vent Valve, B21-F003
- b. Outboard Reactor Head Vent Valve, B21-F004
/ a. PLACE the ADS LOGIC A INHIBIT, B21C-S5A, switch to Ind. Ver. "AUTO."
/ b. PLACE the ADS LOGIC B INHIBIT, B21C-SSB, switch to Ind. Ver. "AUTO."
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- c. VERIFY annunciator AUTO DEPRESS TIMERS INITIATED (A-03 5-1) is clear.
- 35. IF the nitrogen instrument air backup isolation has been overcidden, THEN PLACE the following switches to "0 PEN:"
, f a. DIV I NON-INTRPT, RNA-SV-5262 i Ind. Ver.
,__ / b. DIV II NON-INTRPT, RNA-SV-5261 Ind. Ver.
- 36. IF jumpers were installed to bypass the Vessel Level Grc<.p 1 isolation. THEN REMOVE the following jumperst
- a. UNIT 1 only
/ (1) In Cabinet XU-65, between Terminals 27 and Ind. Ver. 28 on Terminal Board TB-A. ,
/ (2) In Cabinet XU-66, between Terminals 27 and Ind. Ver. 28 on Terminal Board TB-A.
BSEP/Vol. VI/EOP-01-EPP-1P Page 12 of 13 Rev. 6
/ (3) In Cabinet XU-67, between Terminals 27 and Ind. Ver. 28 on Terminal Board TB-A.
/ (4) In Cabinet XU-68, between Terminals 27 and -
Ind. Ver. 28 on Terminal Board TB-A.
- b. UNIT 2 only
/ (1) In Cabinet XU-65, between Terminals 43 and Ind. Ver. 44 on Terminal Board TB-A.
/ (2) In Cabinet XU-66, between Terminals 43 and Ind. Ver. 44 on Terminal Board TB-A.
/ (3) In Cabinet XU-67, between Terminals 43 and Ind. Ver. 44 on Terminal Board TB-A.
/ (4) In Cabinet XU-68, between Terminals 43 and Ind. Ver. 44 on Terminal Board TB-A.
- 37. WHEN the Condensate Feedwater System is no longer needed to maintain reactor vessel level, THEN PERFORM the following steps:
- b. CLOSE the following valves:
__, (1) Feedwater Line A Isolation Valve, B21-F032A ,
__ (2) Feedwater Line B Isolation Valve, B21-F0328
- c. MAINTAIN Feedwater System in long cycle cleanup.
- 38. PLACE Heater Drain System in cold cleanup (OP-35).
- 39. MINIMIZE operations which could dilute boron concentration or spread boron to other support systems.
- 40. MAINTAIN reactor in cold shutdown UNTIL a recovery plan is developed by Plant Management.
- 41. WRITE WR/J0s/LCOs to ensure that functional testing is performed on l those systems in which jumpors were installed.
- 42. WHEN:
- a. Reactor vessel level can be maintained above +170 inches AND
- b. Reactor pressure can be maintained below 1045 psig AND c: . Primary containment parameters are within the limits specified in the Containment Control Procedure.
THElf EXIT this procedure.
BSEP/Vol. VI/EOP-01-EPP-1P Page 13 of 13 Rev. 6
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ATTACHMENT 5 COPY OF CP&L LETTER DATED 1/4/88 TRANSMITTING PROBABILISTIC FIRE ANALYSIS i
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Cp&L Caroline Power & Light Company J AN 0 41988 SERIAL: NLS 88 001 10CFR50, Appendix R United States Nuclear Regulatory Commission
- ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PiANT, UNIT NOS.1 AND 2 DOCKET NOS. 50 325 & 50-324/ LICENSE NOS. DPR-71 & DPR 62 FIRE ANALYSIS Gentlemen:
Carolina Power & Light Company (CP&L) hereby submits the Brunswick Steam Electric Plant (BSEP) Probabilistic Fire Analysis for your review and approval. This analysis included the construction of a detailed computerized fire model for both BSEP units. Each model was heavily based on plant-specific data. A calculation of fire related core damage frequency (CDF) was made for each unit based on this model.
The Company requests early review of this model to achieve the following:
- 1. Confirm its use at BSEP as a tool in fire protection / risk reduction activities.
- 2. Confirm the merit of the met'hodology for possible use at the other CP&L units.
In addition, CP&L is also providing the BSEP Fire Risk Analysis. This analysis is an application of the fire nadel to identify actions needed to reduce fire related CDl' to an internal goal of 3E 5/ year. It 51so avaluates the risk reduction of certain Appendix R modifications and indleates the value of probabilistic risk analysis in meeting the geals of regulatory requirements such as Appendix R. The Company has identified four required Appendix R modifications that provide negligible risk reduction as well as additional administrative contrela not required by Appendix R that provide further reductions in risk. The Company may elect to file exemptions from certain Appendix R - --
requirements that provide negligible risk reduction in order to free the resources needed to pursue the reduction in fire related CDF to the above stated goal.
These documents contain CP&L proprietary information. Therefore, in accordance with 10CFR2.790, the Company requests that they be withheld from public disclosure. An affidavit attesting to this f,tet is included in Attachment 1.
l 1
, 411 Fayettevdte Street e P O Boa 1551
- Asie gm N C 27602 ginatiolo' G i> ,
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Document Csntrol Dask NLS.88 001 / Pcgs 2 Please refer any questions regarding this submittal to Mr. Stephen D. Floyd at (919) 836 6901. ,
Yours very truly, Original sgned By 4, R. Emmerman S. R. Zimmerman Manager Nuclear Licensing Section BAB/bab(\cor\)
Attachments
- ec: Dr. J. Nelson Grace Mr. W. H. Ruland 1
Mr. E. D. Sylvester 1
. ~ . . .
e 4
r Do:usent C ntrol Desk NLS 88 001 / Page 3 bec: Mr. H. R. Banks Dr. J. D. E. Jeffries Mr. R. K. Buckles (L,IS) Mr. L. E. Jones (BNP)
Mr. C. Carmichael (2) Mr. R. E. Lumsden Mr. R. M. Coats Mr. L. H. Martin Mr. A. B. Cutter /MGZ/EJW/SM Mr. C. H. Moseley, Jr.
Mr. C. R. Dietz Mr. J. Moyer (BNP) - -
Mr. S. D. Floyd Dr. G. J. Oliver (BNP)
Mr. B. J. Furr Mr. R. B. Starkey, Jr.
Mr. R. E. Helme (BNP) Mr. B. M. Williams Mr. J. R. Holder (BNP) Mr. T. H. Wyllie (BNP)
Mr. D. E. Hollar File: BC/A 4 Mr. P. W. Howe (BNP) File: B X 0300 s
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' ATTACHMENT 1 AFFIDAVIT i
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AFFIDAVIT OF L. V. EURY County of Wake )
- )SS. - - - - - -
State of North Carolina }
L. W. Eury, being duly sworn according to law, deposes and says as follows: ,
(1) I am Senior Vice President, Operations Support, and I an authorized by Catolina Power & Light Company (CP&L) to review the information sought to be withheld and to apply for its withholding.
(2) I as making this Affidavit in accordance with the requirements of 10 CFR 2.790.
(3) The averments of facts set forth in this Affidavit are true to the best of my knowledge, information, and belief, and that the sources of my information are officers, employees, agents, and contractors of CPGL.
(4) The information sought to be vit.hheld as confidential is contained in Attachments 2 and 3 to NLS 88 001 which is being transmirred herewith.
, Information in Attachments 2 and 3 consists of analyses and sspporting data, relative to the design and operation of the Brunswick Sesam Electric Planc, the application of which could previde a ec=pectcive economic advantage, e.g., by improved reliability and operation of the facility (L0 Cnt 2.790(a)(4)). Pursuant to Sections 2.790(b)(1) amJ (b)(4), I aver that: -
(a) This information is held in confidence by CP4L and is of the -"--
- typo customarily held in confidence by CP&L.
(b) It is CP&L's belief that the facta set forth in this' paragraph provide a rational basis for withholding this information in confidence.
(c) Carolina Power & Light Company is transmitting this information to the NRC in confidence.
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7 (d) This information is not available from public sources in the form in which it is being transmitted.
Further, the Affiant sayeth rot.
AM /
'~l . W ry Sworn tgand subscribed before me this L/ day of December 1987.
sesseeseur,
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My commission expires: 8 -/8 88 I a
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