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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept 1999-07-31
[Table view] |
Text
a h I
.a RPV Level Control E0P 570 Page 1 Rev. 3 i )
. _,/
Unit 1 RPV Level Control Emergency Procedure PAGE NO. EFF. REV.
1-4 3 2a,3a,4a 3 ENTRY CCN0!TIONS:
RPV =ater level less than +4 incres RPV pressure greater than 1085 psig Orywell pressure greater than 2.0 psig An isolation condition exists which requires or initiates a reactor scram A condition which requires a reactor scram and reactor power > 3% or can-not be determined STEPS CBJECTIVES Confire Auto Actions Sucport subsequent actions E0P 570 ex Restore / Maintain Preferred level control band:
) RPV Level Setween (1) Simplifies plant recovery >+8"
+10" and +5o" (2) Prevents Rx Feed Pumo trips <+52"
./
l Alternate level control bard; allows If Level Can t Be increased flexibility during degraded Maintained > +10*.
conditions onlle still saintaining Maintain Level > TAF adequate core cooling
!f Level Can't de Direct operator to contingency actions Maintained > TAF.
Go to E0P 576 in extremely degraded conditions 1
Proceed To Return to normal procedures Cold Shutdo-n
References:
- 1) Emergency Procedure Guidelines, Millstone Unit One
- 2) Emergency Procedure Guidelines, Appendix 8
- 3) Emergency Procedure Guidelines, Appendix C
- 4) ACP-QA-3.02, Attachment A -
- 5) Emergency Plan Implementing Procedure EPIP 4701
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E0P 570 RPV Level Control 8G10 50427 001007 PDR ADOCK 05000213 P PDR
i RPV Level Control E0P 570 Page 2 *
. Rev. 3 .
- 1. PURPOSE The purpose of this procedure is to restore and stabilize RPV water levels.
- 2. ENTRY CONDITIONS 2.1 The entry conditions for this procedure are any of the following:
2.1.1 RPV water level less than +8 inches, 2.1.2 RPV pressure greater than 1085 psig, 2.1. 3 Orywell pressure greater than.2.0 psig, 2.1.4 An isolation condition exists which requires or initiates a reactor scram, 2.1. 5 A condition which requires a reactor scram and reactor power is above 3% or cannot be determined.
- 3. OPERATOR ACTIONS O . .
NOTE:
For Rx Plant degraded conditions, refer to EPIP 4701 for Incident Assessment and Classification.
3.1 Confirm or initiate a Reactor Scram. Perform ONP 502 "Emergency Plant Shutdown" concurrently with this procedure.
- 3. 2 Confirm initiation or initiate the following:
3.1.1 System isolations consistent with plant parameters.
3.2.2 CCc.S sed $8GT operation consistent with plant pa ram.ste rs.
_ 3.2.3 Diesel generator and gas turbine generator operating consistent with plant parameters.
O E0P 570 RPV Level Control
IPV Level Control EP 570 8 age la es ,, )
Syst!4 f 50t. Af f 04 Growo 1 - RPW Low-t.o utter Level (-44") "$1Vs
- daIn 5tese Line mi taa (7 %PPS) Main Steen Liae Oraias ma in Steae Line 41 Flow (120%) (w5 5,6) main Steae Line Teneel M1 Temo (200*F) tectre Loco Sancte Ltae "sin Steae Lire Low Press (82% P in tun) (SM 1,2)
Iso Coad went to "a sta se
(!C-6,7)
Growo 2 IPW Low water Level "(+8*) Orpe l) Ftr Orm (55 3.4)
Cepe11 mi Pressure (2 osig)
.ent ( AC 7) veat self ( AC 9)
Orne11/5wco Cmas ve*t fros As $169 (AC 8)
Dep ell vest to 583f (AC 13)
Swoo Case seat ( AC 11)
" 5.c o l y ( AC 6 )
Oryeell Swcoly ( AC'5)
Orpell/Suco C%as 56 coly (AC 4)
Group 3 iPY Low water Level (*8-) $/0 C1g Systen isstation (50-1.2A.28 aA 48.5) is Head C1g !solatioa (>$ 4)
Growo 4 !so Cond Line Mi 81ow !so Coed Systee !solatics (1 !C 1.2.3,4,6,7)
Growo 5 APV tow-Low =ater Level ( 44*) PwCu Systen Isolettoa j
( CV- 2,2 A ,3,5,23 ) l 5837 auf0 19171Af!C= 150-CC=0 au?O s!f!ar t%
1 w! RA0 in f anawst Pleaos (11 et/me) EPV Low-Low =ater Level (-44*)
2 4! %AO on lefwel Floor (100 et/Mr) IPV Presswre ni (1C85 asig for 3 ;t047 !! !solatten . 15 see) 4 w! ud in Steae Toneel (12 oA/hr)
(005 AVf0-f4fitaf!04 [ftSELCt* av' !*f'! A?!F apt Orne11 mi presswre (2 stig) A=0 APv Low uw eater Levet t tPv tow-Low .eter t.evel ( 44 Th0 Orw ell *1 P esser e (2 asig)
AC !aterloCR (1 C5 or ) I,PCI) d LMP relay SCt atio9 120 SeC If ate (Timed ost)
CJre Soray Orywell Mi Pressdre (2 #sig) 04 025 *.ag ;(4 auf0 lN[?!A?!:%
a PV Low- L ow saterLevel(*44*7 ePy Low Low ester Level ( 43*)
3rpe l t at 8etts.re (2 asig)
L8CI Orwell wi **esswee (2 Jsig) '.3 L8 relay actwat'oa ePV Low Low ' ester Level (-a4* 7 l (OP 570 4PV Level Coetrol O
i
-t-RPV Level Control E0P 570 Page 2 !
[- 3; Rev. 3 i h/ .
- 1. PURPOSE The purpose of this procedure is to restore and stabilize RPV water levels.
- 2. ENTRY CONDITIONS I 2.1 The entry conditions for this procedure are any of the following: .
2.1.1 RPV water level les; than +8 inches, .
2.1.2 RPV pressure greater than 1085 psig, ;
2.1. 3 Orywell pressure greater than 2.0 psig, ;
2.1.4 An isolation condition exists which requires or ;
initiates a' reactor scram, >
i 2.1. 5 A condition which requires a reactor scram and -
reactor power is' above 3% or cannot be determined.
i
- 3. OPERATOR ACTIONS i
NOTE:
i
- For Rx Plant degraded conditions, refer to EPIP 4701 for Incident {
Assessment and Classification.
3.1 Confirm or initiate a Reactor Scram. Perform ONP 502 i "Emergency Plant Shutdown" concurrently with this procedure.
3.2 Confirm initiation or initiate the following: l r
l 3.2.1 System isolations consistent with plant parameters. {
3.2.2 ECCS and SBGT operation consistent with plant l parameters. }
1
\
3.2.3 Diesel generator and gas turbine generator operating i
' consistent with plant parameters, j i
I i !
]
- O l
E0P 570 RPV Level Control
'I i
RPV Level Control E0P 570 Page 3a Rev. 3 l I. CONDITIONS REQUIRING RPV FLOODING A. RPV Level Control (EOP 570)
- 1. RPV water level cannot be determined.
B. Containment Control (EOP 580)
- 1. Drywell temperature reaches the RPV Saturation Temperature.
- 2. Suppression Chamber pressure cannot be maintained belcw the Primary Containment Design Pressure.
C. RPV Level Restoration (EOP 576)
- 1. RPV water level cannot be determined.
O. RPV Level /Rx Power (EOP 575)
- 1. RPV water level cannot be determined, and Rx Power cannot be determined or raintained aoove 8%.
II. BORON INJECTION REQUIREMENTS A. Rx Power Control (EOP 572)
- 1. If the Rx is not shut.down and Suppression Pool Temperature reaches 110*F.
O E0P 570 RPV Level Control
I RPV Level Control E0P 570 Page 3 3_ Rev. 3 (U
'l When executing the following steps:
E Boron Injection is required, THEN GO TO E0P 575 "RPV Level /Rx Power".
E RPV water level cannot be determined, RPV Flooding is required, THEN GO TO E0P 578 "RPV Floodir.g". ,
E RPV Flooding is requir*' for other reasons THEN GO TO E0P 578 "RPV Flooding".
A.AAAAA.224.A.AAAAAAAAAAAAAAAA AA AAAAAAAAAAAA.AAAAA AAA AAAA ARA..AAAAA CAUTION Avoid RPV high water level trip (+52") of reactor feedwater pumps.
CAUTION Oo not secure or plar.e an ECCS in Manual mode unless by at least two O
U independent indications:
- l. Misoperation in automatic is confirmed, OR
- 2. Adequate core cooling is assured.
If an ECCS is placed in Manual, it will not initiate automatically. Make f requent checks of the initiating or controlling parameter. WMen manual operation is no longer required, restore the system to automatic / standby if possible.
CAUTION If a high drywell pressure ECCS initiation signal 2.0 psig occurs or exists while depressurizing, prevent injection from those CS and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressure. When the high drywell pressure ECCS initiation signal clears, restore CS and LPCI to AUTOMATIC / STANDBY mode.
..A.A.......A.........A........................A..A....A..............A.
O -
E0P 570 RPV Level Control
9 RPV Level Control ECP 570 Page 4a Rev. 3 CONDITIONS REQUIRING ALTERNATE SHUTDOWN COOLING A. RPV Pressure Control (EOP 571) {
- 1. If RPV cooldown '- required but cannot be accomplished AND all control rods -
are inserted beyond position 04.
l l
l 1 O l
l l ,e O
E0P 570 RPV Level Control'
s RPV Level Control E0P 570 Page 4
- y Rev. 3 G'
3.3 Restore and maintain RPV water level +10" - +50" with one or more of the following systems, consistent with existing RPV pressure.
Make-up Make up System System OP RATED FLOW Pressure Range 6
____ C o nt FW '31.5/316 7.9 x 10 lbm/hr 2300 psig - O psig
~~~~
CR0 ; isch t 302 200 GPM 1500 psig - O psig
,_,' - 336 3600 GPM/ Loop 330 psig - O psig
~~ ~
it'I ps os. 3J5 15,000 GPM 250 psig - O psig
- 3. 3. 4 ;F RP'> watar level cannot be maintained above +10",
.~19N maintain RPV water level above -127" (TAF)
/~'N 3.3.2' IF RPV water level can be maintained above -127" k, s [T.4), AND the APR timer has initiated, TH5h prevent automatic RPV depressurization by depressing the APR Timer Reset pushbutton and CONTINUE to reset every minute UNTIL, RFV water level is > -48", OR Drywell pressure is ( 2 psig and the "High Orywell Pretsure Reset" key is in the reset position, OR All Core Spray and LPCI pumps are not running, AND the "APR Auto-Blowdown A/C Interlock" alarm is clear.
IF to'! water lev;l has not stabilized and approaches -127" (TAF),
ThEN 00 .a E0P $76 "RPV Level Restoration" IF Alternate Shutdown Cooling is required IEN GO TO E0P 579 "Alternate Shutdown Cooling".
3.4 WHEN OP 206 "Plant Cooldown to Cold Shutdown" is entered from E0P 571 "RPV Pressure Control" at Step 3.7.
s THEN GO TO OP 206 "Plant Cooldown to Cold Shutdown." ,
U(N RP:j1c FINAL E0P 570 RPV Level Control
STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number: E0P 570 Rev. 3
Title:
RPV LEVEL CONTROL EMERGENCY PROCEDURE Prepared By: EO BERRY ,
- 8. REVIEW '
I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD ).
/'/// /
S* $~
Ybt t<J.
V V/7-$
C. SPECIFIC UNREVIEVED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and cnanges operation of systems as described in design documents. YES ( ] NO ( @
(If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO ( T
- 0. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO (1 (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E. INTEGRATED SAFETY EVALUATION REQUIRED YES ( ) NO ( 7 F. PROCEDURE RECUIRES PORC/50RC REVIEW (In addition to review, items with a YES response must be documented in the PORC/50RC meeting minutes.)
f YES T ] NO ( )
G. USORC APPROVAL SORC Meeting Number / ~ d'd - Y H. APPROVAL AND IMPLEMENTATION The attacned procedure is hereby approved, and effective on the date below:
h /$ & hO $b sta,*fon/ Sarvice//Jnit Superintendent Ef fective/Date SF301/9/s/SES/97-12/lofi s
-