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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
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Stephen E. v e9 3-31-87 87-12 Form Appr;v:d by Stat'..n Sup;rint:ndent Effective 0. ] 50RC Mtg. No.
STATION PROCEDURE COVER SHEET
/h A. IDENTIFICATION U
Number: E0P 35 FR-I._3 Rev. 2 i
Title:
ESPONSE TO VOIDS IN REACTOR VESSEL Prepared By: H. K. COVIN B. _ REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD G//
C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO [ 4 (If yes, perform written USQ determination and Safety l Evaluation, and contact Manager, Safety Analysis Branch to
- determine need for Integrated Salety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO [ 7
- 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 [-]
(If yes, perform written Safety Evaluation snd i contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO[Y F. PROCE9UPE REQUIRES ORC REVIEW (In addition to review, it with a YES response /
must be documented in th PO /SORC meeting minutes.) YES [d NO [ ]
G. hSORCAPPROVAL SQRC Meeting Number L y 7- ///7 H. APPROVAL AND IMPLEMENTATIC'N The attached to ei reby approved, and effective on the date below:
_ _- dlll' - # - / [ '
Station / Service / Unit Superintendent Effective Date
~
SF 301 Rev. 9 Page 1 of 1 8810260571 00100723 i PDR ADOCK 050 P
E0P 35 FR-I.3 Page 1 )
. Rev. 2 I
RESPONSE TO VOIDS IN REACTOR VESSEL l
Page No. Ef f. Rev. l 1 1-10 2 Attachment A 2 l t
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ntsrvNsE TO VOIDS IN REAGTOR VESSEL E0P 35 FR-I.3 Pags 2 Rev. 2
(
A. PURPOSE This procedure provides actions to respond to voids in the reactor !
vessel head.
6 B. ENTRY CONDITIONS This procedure was written for Modes 1, 2, 3, and 4 assuming SI has been terminated. Using this procedure when not in these modes 1
requires a step by step evaluation to determine if the required action is still 9plicable to current plant conditions.
This procedure is entered from E0P 35 F-0.6, INVENTORY Critical Safety Function Status Tree on a YELLOW condition. l 4
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O RESPONSE TO VOIDS IN REACTOR VESSEL EOP 35 FR-1.3 Pags 3 Rev. 2
)
STEP ACTION /EMPECTED RESPONSE RESPONSE NOT OSTAINED ,
CAUTION 6
If a controlled natural circulation cooldown is in progress and a void in the reactor v-ssel upper head is expected, this procedure should not be performed.
~ r 1 Check If SI Has Been Return to procedure and step in .
Te rminated effect.
SI pumps - ALL STOPPED
- a. Charging Pump to ,
Cold Les Injection , i Valves - CLOSED ;
2 Check If Charging Flow Has Been Established I
- a. Verify Recire a. Establish Recirc Flowpath i Flowpath - ESTABLISHEb
! O b. Charging pump -
AT LEAST ONE RUNNING
- b. Perform the following i
- 1) IF RPCCW flow to RCP thermal barriers is 4
lost, THEN isolate ,
seal injection to affected RCP before starting charging pump. *
- 2) Start one charging !
4 Pump, t 3) IF seal injection was ,
, isolated THEN
)
I resture seal .
j injection to RCP's '
l
, c. Instrument Air to c. Establish instrument air i Containment - ESTABLISKED to containment. (
- 1) One instrument air r compressor running j
- 2) OPEN instrument air ,
i containment isolation !
valves l
P ove.ou.i m i
RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Paga 4 Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO
- d. Charging flow - d. Establish Normal ES TABLISHED charging flow IF charging can NOT be established, THEN establish excess letdown as per OP 3304A, CHARGING AND LETDOWN Go to Step 4.
3 Check Letdown - IN Ests;blish letdown SERVICE Ir, letdown can NOT be established, THEN establish excess letdown as per OP 3304A, CHARGING AND LETDOWN, ,
4 Establish Stable RCS Conditions
- a. PZR level - STABLE a. Control charging and AND BETWEEN 40% AND letdown as necessary.
60%
J I
() b. RCS pressure - STABLE b. Turn on PZR heaters and use normal PZR spray as necessary. IF normal
]
- spray NOT available and letdown in service, THEN use auxiliary spray.
1 i c. RCS hot leg c. Dump steam as necessary.
temperatures - ST/BLE f, 5 Check RCPs - ALL STOPPED Go to Step 12.
if 1
4 O
OP$0641 344
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i KE5rvNst TO VOIDS IN REAGTOR VESSEL EOP 35 FR-I.3 Pogs 5 l Rev. 2 fi STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OOTAINED 6 Check If RCS Pressure Should Be Increased l
- a. Pressure - AT LEAST s. Go to Step 9, ;
100 psi < TECH SPEC f LIMIT on Figure 3.4-3 l
- b. Pressure < 1850 psia b. Go to Ster 4. l (2120 psia FOR !
ADVERSE CONTAINMENT)
- c. Turn on PZR heaters to increase RCS pressure 50 psi ;
7 Control Charging And Letdown As Necessary To ,
Maintain PZR Level .
>17% (50% FOR ;
ADVERSE CONTAINMENT)
- NOTE i Several increases of pressure may be necessary before RVLMS will ,
I i actually indicate level is increasing in the head.
1 !
% 8 Check RVLMS head AND plenum ,
level indication l
- a. Indication - INCREASING a. Go to Step 9. i l
- b. Head AND plenum - 100% b. Return to Step 6.
i l c. Turn off PZR heaters 6 i as necessary to stabilize RCS pressure l
- d. Return t; procedure and
, step in effect l
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w RESPONSE TO VOIDS IN REACTOR VESSFL E0P 35 FR-1.3 Psge 6 Rev. 2 r
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STEP ACTION /EXPECTIO RESPONSE RESPCNSE NOT 09TAINGO CAUTION If seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation.
NOTE l,
RCPs should be run in order of priority (2, 1, then 3 or 4) to provide normal PZR spray.
9 Try To Start One kCP e
- a. Establish the following a. IF conditions can NOT conditions prior to RCP be established, THEN start go to Step 12.
- 1) PZR level >90%
(90% FOR ADVERSE
[
CONTAINMENT)
- 2) RCS subcooling based O- on core exit TCs
>70*F (125'F FOR ADVERSE CONTAINMENT)
- 3) Prepare RCP for operation as per OP 3301D, REACTOR COOLANT PUMP OPERATION,
- b. Start one RCP 10 Check RVLMS head AND Go to Step 12.
plenum level - 100%
- 11 Go To Step 21 12 Determine containment hydrogen Obtain a containment hydrogen concentration per OP 3313A, concentration measurement ilYDROGEN RECOMBINERS, with the Post Accident HYDROGEN MONITORS AND Sampling System RECOMBINER BLDG VENTILATION O
OPD004-1 S-84
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nzsrunss To volus IN REALTUR VE5YET. E0P 35 FR*I.3 Pags 7 l Rev.'2 '
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STsP ACTION /EXPECTIO RESPONSE RESPONSE NOT OSTAINED CAUTION Following block of automatic SI actuation, manual SI act.uation may be required if .
conditions degrade.
13 Check If Low P2R Pressure SI Can Be Blocked
- a. P7R pressure <1950 psia a. Decrease P~' 'jres su re to <1950 r 6 using normal P2
- pray. IF normal ar-ay NOT l
avai}ableandletdown in service, THEN use !
auxiliary spray. IF l NOT, THEN use one PZR l PORV.
l
- b. Block Low PZR Pressure SI 14 Record RCS Pressure psia !
15 Establish Following RCS Conditions
- a. PZR level - STABLE a. Control charging and AND BETWEEN 40% AND letdown as necessary.
60%
- b. RCS pressure - STABLE b. Turn on PZR heaters and ,
use normal PZR spray as [
nece s s a ry. IF normal l spray NOT available and (
letdown in service, THEN i use auxiliary spray. [
t
- c. RCS subcooling based c. Dump steam as necessary.
l on core exit TCs !
>80*F (140*F FOR j j ADVERSE CONTAINMENT)
I
- d. RCS hot leg tempera- d. Dump 2 35- as necessary. [
j tures - STABLE [
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RESPONSE TO VOIDS IN REACTOR VESSEL EOP 35 FR-1,3 Peg 2 8 Rev. 2 i
(D STEP ACTION /tKPECTED RESPONSg MESPONSE NOT OSTAIN80
__16 Prepare for Reactor Vessel l Venting
- a. OPEN both Rx Vessel a. IF either valve in one Head Vent Isolation train fails to open valves (one Train THEN close both valves only) and open both valves in other train.
- b. IF PRT not available, '
THEN consult with Director of Station Emergency Organization t (DSEO) l NOTE The following step is completed in case.a PRT rupture disc fails while venting the Rx vessel to the PRT.
17 Determine Maximum Allowable Venting Time
- a. Containment hydrogen a. Decrease hydrogen O- concentration <3% concentration by operating H l
2 !
recombiners per OP 3313A, NYDROGEN !
RECOMBINERS AND ;
RECOMBINER BUILDING
- b. Refer to ATTACHMENT !
A to determine [
maximum venting time .
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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Page 9 Rev. 2 s -
STEP ACTIOM/tXPECTRO RESPONSE RESPONSE NOT 08TAINE0 18 Review Reactor Vessel Venting Termination Criteria
- a. RCS su'> cooling based on core exit !
TCs <30*F (90'F FOR l !
ADVERSE CONTAINMENT) l 1
0
- b. PZR level <17% (50% !
FOR ADVERSE CONTAINMENT) l.
OR t
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- c. RCS pressure - DECREASES ,
, B)' 200 psi .
OR i
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- d. Venting time - GREATER t i
THAN MAXIMUM TIME l CALCULATED IN STEP 17 i (IF a PRT rupture disc
, has failed)
- OR l f
- e. RVLMS head and plenum I level - 100% [
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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Paga 10 Rev. 2
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RESPONSE NOT OSTAIN80
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STEP ACTION /EXPEi:TSO RESPONSE '
CAUTION Venting should be stopped if any venting termination criterion in Step 18 is exceeded.
19 Vent Rx Vessel
- a. Throttle OPEN one a. IF one valve fails to Rx Vessel Head Vent open THEN throttle OPEN Controller other valve.
l
- b. Any vaating termin- b. Cont}nue venting. WHEN" ation criterion - any venting termination EXCEEDED criterion is exceeded.
THEN go to Step 19c.
- c. CLOSE all Vent Valves O _ 20 Check RVLMS head AND plenue level - 100%
'ncrease RCS pressure to value
.acorded in Step 14.
to Step 12, Return 21 Check PZR Level - STABLE Control charging and letdown as necessary.
22 Return To Procedure And Step In Effect
-FINAL-O OPK6M 344
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RESPONSE TO VOIDS IN REACTOR VESSEL E0P 35 FR-I.3 Pega 1 of 1 Rev. 2
~
O ATTACHMENT A INSTRUCTIONS FOR DETERMINING VENTING TIME
- 1. Determine Containment Volume at STP = A P 492*R 6 3 A = (2.26 x 10 gg ) x 14.7 psia x T where: P (psia) = Containment pressure (psia)
T (degrees R) = Containment temperature (degrees F) + 460
- 2. Determine Mtximum Hydrogen volume that can be vented = B (3.0% - Containment Hydrogen Concentration) x A B= 100%
- 3. Determine Hydrogen flow rate as a function of RCS pressure = C
- a. Check RCS pressure,
- b. Using OPS FORM E0P 35 FR-I.3-1, read hydrogen flow rate. l
- 4. Calculate maximum venting time:
Maximum venting time = B C
O OP9004 2 344
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FORM APPROVED BY LTNI'T 3 SUPERINTENDENT
&/a/a EFFECTIVE DATE 3-871vr PORC MTG NO 1
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