Letter Sequence Other |
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Results
Other: GO2-86-104, Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency), GO2-86-310, Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 1986, GO2-86-656, Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs, GO2-87-019, Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns, GO2-87-034, Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14), GO2-87-179, Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas, GO2-87-232, Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire, GO2-88-008, Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR, GO2-88-111, Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 880513, GO2-88-136, Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources, GO2-88-155, Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER, GO2-88-156, Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 880801, GO2-88-157, Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request, GO2-88-168, Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration, GO2-88-209, Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects, GO2-88-214, Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-10, GO2-88-222, Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting, GO2-89-035, Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 890417, ML17278B122, ML17278B182, ML17279A257, ML17279A778
|
MONTHYEARGO2-86-310, Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 19861986-04-0404 April 1986 Forwards Advance Copy of Update of App F Re Fire Protection Evaluation for Facility Fsar.Update Will Be Formally Submitted as Amend 37,currently Scheduled for Issue in June 1986 Project stage: Other GO2-86-656, Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs1986-07-16016 July 1986 Responds to 860314 SER Implying That App R Analysis Requirements Performed for high-pressure-to-low-pressure Sys Interfaces Must Assume That Two Spurious Actuations Occur Simultaneously.Position Contrary to Generic Ltrs Project stage: Other ML17278B0471986-10-20020 October 1986 Forwards Request for Addl Info Re Current Condition of Unit 2 Compared to Regulations,License & Commitments to Fire Protection Program.Requests Response within 30 Days of Ltr Receipt Project stage: RAI ML17278B0461986-10-21021 October 1986 Discusses 861002 Meeting W/Ofc of General Counsel & Plant Sys Branch Re Plant Approved Fire Protection Program.Meeting Concluded That Program Includes Written Communications Docketed Prior to Issuing OL Project stage: Meeting ML17278B1221986-11-17017 November 1986 Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency) Project stage: Other GO2-86-104, Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency)1986-12-0101 December 1986 Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency) Project stage: Other GO2-87-034, Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14)1987-01-29029 January 1987 Forwards Fire Protection Program Description in Response to 870113-15 Fire Protection Insp to Facilitate Implementation of License Condition 2.C(14) Project stage: Other ML17278B1821987-02-0505 February 1987 Informs That Attachment to Will Be Considered Approved Fire Protection Program.Approval of Program Contingent on Timely Submittal of License Amend Request Per Generic Ltr 86-10 Project stage: Other ML17279A2571987-05-13013 May 1987 Advises That Util Required to Implement Appropriate Mods to Isolation Valves RHR-V-8 & RHR-V-9 to Meet Objectives of App R to 10CFR50 Re Prevention of LOCAs at High/Low Pressure Interfaces.Submittal of Schedule Requested Project stage: Other GO2-87-179, Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas1987-05-27027 May 1987 Forwards Response to Unresolved Items Noted in Insp Rept 50-397/87-02.Corrective Actions:Independent Insp by Consultants Confirmed That Detection Sys Meets Requirements for safety-related Areas Project stage: Other GO2-87-019, Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns1987-06-0303 June 1987 Forwards Info Re Mods Proposed to Ensure Isolation of RHR-V-8 or RHR-V-9 Valve & Schedule for Completion of Mods, Per 870513 Request Re Generic Ltr 86-10 Interpretation of High/Low Pressure Interface Concerns Project stage: Other GO2-87-232, Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire1987-08-20020 August 1987 Responds to Generic Ltr 86-10.Util Determined That Providing Transfer Switch on Remote Shutdown Panel for RHR-V-8 Valve Preferred Method for Ensuring Isolation of Either RHR-V-8 or V-9 in Event of Control Room Fire Project stage: Other ML17279A5771987-10-0202 October 1987 Recommends That Meeting Be Held to Ensure Completion of Mods to Preclude Spurious Opening of High Low Interface Valves in Event of Control Room Fire,Per NRC 870513 Request & Util 870820 Response Project stage: Meeting ML20236N1261987-11-11011 November 1987 Safety Evaluation Supporting Amend 37 to FSAR Re Fire Protection Program Project stage: Approval ML17279A7781987-12-23023 December 1987 Discusses 871002 Response to Re Util Preferred Course of Action for Precluding Spurious Opening of high-low Interface Valves RHR-V 8 & RHR-V-9 in Event of Control Room Fire.No Submittal on Subj Received to Date Project stage: Other GO2-88-008, Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR1988-01-11011 January 1988 Responds to Inconsistencies Noted in Introduction to SER Forwarded by Gw Knighton .Ser Addressed Fire Protection & Safe Shutdown Capability Per Amend 37 to FSAR Project stage: Other ML17279A7751988-01-13013 January 1988 Notification of 880119 Meeting W/Util in Bethesda,Md to Discuss Fire Protection Plan & Util Responses to NRC Comments on Plan Project stage: Meeting ML17279A8881988-03-0909 March 1988 Summary of 880119 Meeting W/Util in Bethesda,Md Re Util Responses to 28 Fire Protection Questions Raised in NRC .Attendee List Encl Project stage: Meeting GO2-88-111, Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 8805131988-05-0606 May 1988 Informs That Rev to Plant Procedure 1.3.10, Fire Protection Program, Committed to in 870128 Response to Insp Rept 50-397/86-25,currently in Process to Incorporate Listed Addl Changes.Procedure Will Be Revised by 880513 Project stage: Other GO2-88-136, Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources1988-06-0303 June 1988 Informs That Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Rescheduled for Completion from 880515 to 880715 Due to Unavailability of Supporting Resources Project stage: Other GO2-88-155, Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER1988-07-15015 July 1988 Forwards Calculation Analyzing Structural Integrity of Specific Support Steel Configurations for Instrument Sensing Lines Re Fire Protection & Safe Shutdown Capability Response to SER Project stage: Other GO2-88-157, Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request1988-07-15015 July 1988 Forwards Completed Executive Summary of App R High Impedance Fault Analysis,Per NRC 880606 Request Project stage: Other GO2-88-156, Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 8808011988-07-15015 July 1988 Provides Schedule for Completion of Fire Protection Issues from Insp Rept 50-397/88-16.Installation of Scuppers on South Doors Leading Outside Diesel Generator Bldg Will Be Completed by 880801 Project stage: Other GO2-88-163, Submits Clarification of Approved Fire Protection Program Per 880610 Exit Meeting,Covering Plant Design,Door Openings, Fire Barriers,Fire Dampers & Doors & Safe Shutdown Capability1988-07-26026 July 1988 Submits Clarification of Approved Fire Protection Program Per 880610 Exit Meeting,Covering Plant Design,Door Openings, Fire Barriers,Fire Dampers & Doors & Safe Shutdown Capability Project stage: Meeting GO2-88-168, Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration1988-07-29029 July 1988 Responds to NRC Re Violations Noted in Insp Rept 50-397/88-19.Corrective Actions:Instrument Rack Termination Procedure PPM 10.25.19 Will Be Revised by 890315 to Include Examples of Acceptable Crimp Configuration Project stage: Other GO2-88-209, Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects1988-09-30030 September 1988 Submits Revised Response to SER Question 25 Re Fire Protection & Safe Shutdown Capability.Analysis Performed to Identify high-to-low Pressure Interface Valve Motor Power Feeder Requiring Protection Against Fire Related Reconnects Project stage: Other GO2-88-214, Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-101988-10-0707 October 1988 Forwards Updated Schedule of Commitments for Completion of Fire Protection Issues,Per Concerns Noted in Insp Rept 50-397/88-16 & Open Items Noted During Fire Protection Audit on 880606-10 Project stage: Other GO2-88-222, Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting1988-10-28028 October 1988 Submits Revised Response to Insp Rept 50-397/88-16 Re Fire Protection & Safe Shutdown Capability.Fire in Drywell Expansion Gap Has Very Low Probability of Starting Project stage: Other GO2-88-250, Clarifies Min Staffing Needed for Safe Shutdown Re Insp Rept 50-397/88-16 Dtd 880725.Util Understands That Any Combination of Personnel Meeting 10CFR50,App R Requirements Acceptable1988-11-28028 November 1988 Clarifies Min Staffing Needed for Safe Shutdown Re Insp Rept 50-397/88-16 Dtd 880725.Util Understands That Any Combination of Personnel Meeting 10CFR50,App R Requirements Acceptable Project stage: Meeting GO2-89-035, Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 8904171989-03-0606 March 1989 Provides Revised Schedule Dates for Commitments Made in Response to Violations Noted in Insp Repts 50-397/87-19 & 50-397/88-41.Plant Procedures 10.25.19 & 11.2.1.2 Will Be Issued by 890417 Project stage: Other 1987-06-03
[Table View] |
Text
. SAFETY RELATED CONTROLLED COPY
+>>>00272 Bgippg.
%re SUPPLY SYSTEM F
PDFt I PLANT PROCEDURES MANUAL MINP-2 PROCEDURE NUMBER
+5.3.6 APPROVE DATE 11/17/86 5
EMERGENCY PROCEDLQS 5.3 EMERGENCY PROCEDURE CONTINGENCIES
~5.3.6 RPV FLOODING (CONTINGENCY) l.
If at least 3 SRV's are open or if the HPCS pump is available for injection, close:
a.
MSIV's b.
Main Steam Line Drains:
MS-V-16 MS-V-19 c.
RCIC Steam Isolation Valves:
RCIC-V-8 RCIC-V-63 RCIC-V-76 (C-FLD)
PROCEDURE NlgHBgR 2 ~ 0 1 REVISION NUMBER PAGE NUMBER 5.3.6.-1 of 15
'P-517 R3 I2/88)
. SAFETY RELATED Number of'pen SRVIs CONTROLLED COPY l
Alternate RPV Flooding Pressure (psig) 7 or more 6
5 4
2 185 215 265 330 445 675 (C-FLO)
PROCEDURE NUMBER 5.3.6 WP 999 RI (9.99)
REVISION NUMBER PAGE NUMBER 5.3.6-2 of'5
,, SAFETY RELA D
tONTROLLED COPY ol rod is not inserted beyond position 06:
2.1 Terminate and prevent all injecticn into the RPV except from boron injection systems and CRD until RPV pressure is beLow the Alternate RPV Flooding Pressure.
Even if less than 2 SRVs can be opened, continue in this procedure.
If while executing Steps 2.2 and, 2.3, RPV water level can be determined and RPV flooding is not required, exit this procedure and enter:
o PPM 5.3.7, Level/Power Control (Contingency) o PPM 5.1.2, RPV Pressure
- Control, (RPV/P) Step 10.
and execute those procedures concurrently.
(C-FLO)
PROCEOURE NUMBER 5.3.6 REVISION NUMBER PAGE NUMBER 5.3.6-3 of 15 WP 594 RI (9 45)
SAFETY RELA CONTROLLED COPY CAUTION (2.2)
A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.
I I "
Alternate RPV Number of open SRV's I Flooding Pressure (psig) 7 or more 6
5 4
2
'185 215 265 330 445 675 (C-FLO)
PROCEDURK NUMBKR 5.3.6 RKVISIQN NUMBKR PACK NUMBER 5.3.6-4 of'5 WP $ 99 RI {9 93)
. SAF,ETY RELAY CAUTION
%ONTROLLED COPY 2.2 Comtl.nce and slowly raise injection flow into the RPV with the following systems until at least, o
Two SRV's are open and, o
RPV pressure is above the Alternte RPV Flooding Pressure:
a.
CRO 1DO-0 psig I
b.
Condensate/Condensate Booster -. - - - -
460-0 psig 1)
Verify RFW-LIC-620 in MANUAL and RFW-FCV-10 closed.
2)
Open:
RFW-V>>117A RFW-V-117B RFW-V-118 3)
Close:
RFW-V-112A RFW-V-112B 4)
Start at least one condensate pump and one condenstate booster pump.
5)
Slowly open RFW-FCV-10 while monitoring RPV pressure.
6)
If RFW-LIC-620 output exceeds 90%, verify RFW-FCV-15 is closed.
7)
Start another condensate/condensate booster pump.
8)
.Jog RFW-V-109 open.
(C-FLO)
IaRQCKDURK NUMBKR 5.3.6 RKVISION NUMBKR PAQK NUMBKR 5.3.6-5 of 15
- WPi$94 RI (9 4$ )
SAFETY RELA'T Number of open SRV's CONTROLLED COPY I
Alternate RPV Flooding Pressure (psig) 7 or more 6
5 4
2 185 215 265 330 445 675 CAUTION (2.3.a)
A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.
(CWLO)
PROCEDURE NUMBER 5.3.6
'%VP $94 R1 {9 44)
REVISION NUMBER 2
PAGE NUMBER 5.3.6-6 of 15
. SAFETY RELA D
CONTROLLED.COPY o
At least 2 SRV's are not open or, o
RPV pressure carrot be increased above the Alternate RPV Flooding Pressure, commence and slowly raise injection flow into the RPV with the following systems until at least, o
Two SRV's are open and, o
RpV pressure is above the Alterate Rpv Flooding pressure:
CAU a.
HPCS 1130-0 psig 1)
Align HPCS to take suction from the suppression pool.
2)
At H13-P625, block open contacts 1-2 of relay E22A-K3.
3)
Verify HPCS-V-4 is closed.
4)
Start HPCS-P-l.
5)
Open HPCS-V-23.
6)
Open HPCS-V-4.
7)
Jog HPCS-V-23 closed while monitoring RPV pressure.
b.
LPCS c.
Standby Service Water 1)
Use only if RHR-P-2B is inoperable.
2)
Close RHR-V-42B.
360-0 psig 160-0 psig 3)
At H13-P623, block open contacts 9-10 of relay B22H-K30.
4)
Verify SW-P-1B operating.
5)
Open RHR-V-115 and RHR-V-116.
6)
Wg open RHR-V-53B while monitoring RPV pressure.
7)
Close RHR-V-68B.
(C-FLO)
PROCEDURE NUMBER 5.3.6 WP SQI Rl {t.SS)
REVISION NUMBER PACK NUMBER 5.3.6 7 of 15
SAFETY RELA Number of open SRV's CONTROLLED COPY I
Alternate RPV Flooding Pressure (psig) 7 or more 6
4 2
185 215 265 330 445 675 (cwLo)
PROCEOURE NUMBER 5.3.6 WP $ 9$ R'I I9.99)
REVISION NUMGKR PAGE NUMBER 5.3.6-8 of 15
SAFETY RELAY CONTROLLED COPY zn ain at least 2 SRV's open and RPV pressure above the Alterate RPV Flooding Pressure by throttling injection..
2.5 When:
o All control rods are inserted beyond position 06 or, o
The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure.
If RPV water level cannot be determined:
3.1 Commence and increase injection into the RPV with the following systems util at least, o
Three SRV's are open and, o
RPV pressure is not decreas'ng
- and, o
RPV pressure is not decreasing and is at 3,east 100 psig above suppression chamber pressure:
a ~
HPCS b.
CRD 1130-0 psig 1130-0 psig c ~
Condensate/Condensate Boosters 460-0 psig d.
LPCS 360-0 psid e.
LPCI 220-0 psid Use Standby Service Water only if RHR-P-2B is inoperable.
f.
Standby Service Water- - - - - -160-0 psig 1)
Verify SW-P-1B operating 2)
Open RHR-V-115 and RHR-V-116 3)
Open RHR-V-42B 4)
Close RHR-V-68B (CWLO)
PROCKDURK NUMGKR 5.3.6 WP 599 RI (9.99)
RKVISION NUMBKR PACK NUMKKR 5.3.6-9 of 15
SAFETY FIELA ire Water RomaoLLeo co< v 90-0 psig 1)
String f'ire hose from nearest outside hydrant to COhO-P-2A.
2)
Attach hose to adaptor at COND-P-2A suction.
3)
Open hydrant and adaptor shutoff valves.
h.
SLC (test tank if DW-P-lA or DW-P-18 is operating) i.
SLC (boron tank) 3.2 Maintain at least 3 SRV's open and RPV pressure at least 100 psig above suppression chamber pressure by throttling injection.
4.
If RPV water level can be determined, comnence and increase injection into the RPV with the following systems until RPV water level is increasing:
a.
HPCS b.
CRD 1130-0 psig 1130-0 psig c.
Condensate/Condensate Boosters 460-0 psig d.
LPCS e.
LPCI NOTE 360-0 psid 220-0 psid Use Standby Service Water only if RHR-P-2B is inoperable.
f.
Standby Service Water- - - - - -160-0 psig 1)
Verify SW-P-1B operating 2)
Open RHR-V-115 and RHR-V-116 3)
Open RHR-V-428 4)
Close RfR-V-68B g.
Fire Water 90-0 psig 1)
String fire hose from nearest outside hydrant to COID-P-2A.
(C-FLD)
PROCEDURE NVMBKR 5.3.6 WP 999 RI I$.93)
REVISION NUMBER PAGE NUMBKR 5.3.6-10 of l5
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SAF.ETY RELAY A
CONTRQLLED COPY 60 MAXIMUMCORE UNCOVERY TIME LIMIT 60 I
2 g
40 IC 30 8
Pc V
O 20 10 10 1000 TIME AFTER REACTOR SHUTDOWN (MIN)
(c~)
PROCKDVRK NUMSKR 5'.l.6 RKVIS ION N VM8KR PAGK NVMBKR g.S.I5-12 Of M>
WP $90 Rl (9 99)
I
SAFETY RELA CONTROLLED COPY e injecting water into the RPV until water level instrumentation is available.
If while executing Steps 5.3 and 5.4, RPV water level can be determined, continue in this procedure at Step 6.
5.3 Determine the RPV is filled by three or more of the following methods:
a.
RPV level indications upscale on fuel zone, wide range and narrow range channels.
b.
RPV skin temperature drop coincident to initiation of flooding with sustained downward trend.
c.
SRY acoustic monitors on open SRVs indicate flow.
d.
SRV tailpipe temperature comparison indicates flow.
e.
Restart of RRC-P-1A or RRC-P-1B provides stable jet pump flow indication.
5.4 If it can be determined that the RPV is filled or RPV pressure is at least 100 psig above suppression chamber pressure, term-inate all injection into the RPV and reduce RPV water level:
Terminated Injection a.
Open RPV head vents MS-V-1 and MS-V-2.
b.
Confirm SRV's open.
c.
Open RHR-V-67 until approximately 6 additionaL inches of stem have been exposed.
d.
Open RHR-Y-8 and RHR-V-9.
e.
Close RHR-Y-S, RHR-V-9, and RHR-V-67 when either level indication comes on scale or before exceeding the Maximum Core Uncovery Time Limit.
5.5 If'PV water level indication is not restored within the Maximum Core Uncovery Time Limit after commencin termination of injection into the RPV, returns step QE (COLD)
PROCEOURK NUMBER 5.3.6 WP.999 R'I (9 93)
REVISION NUMBKR PAGE NUMBER 5.3.6-13 of'5
SAFETY RELAY CONTROLLED COPY PRIMARY CONTAINMENTDESIGN PRESSURE 70 60 U
th Cl.
w 50 Cll Cil W
CL 40 PI Cl 30 O
ch Cll 20 C
CL Cll 10 CSP 00 FT 99.9 PS CC PT 0
10 20 30 40 50 60 SUPPRESSION POOL WATER LEVEL(FT.)
~llll9$
(~LD)
PROCEDURE NUMBER 5.3.6 REVISION NUMBER PAGE NUMBER 5.3.6-14 of 15 WP SOS Rl (9 $ 3)
SA%'ETY RELAY 0 CONTROLLED COPY sion chamber pressure can be maintained below the Primary Containment Design Pressure,'xit'this procedure and enter:
o PPH 5.1.1, RPV Level Control, (RPV/L) Step 5.1.1.4.2
- and, I
o PPM 5.1.2, RPV Pressure
- Control, (RPV/P) Step 5.1.2.4.10 and execute those procedures concurrently.
(C~LD)
PAOCKOURK NUMBER 5.3.6 WP IIIIRl (0%II REVISION NUMBER PACK NUMBER 5.3.6-15 of 15