|
---|
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
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _
E. J. Mroc2 1-1-85
. Fora Approved by Station Superintendent Effective Onte l STATION PROCEDURE COVER SHEET
/N 1
h A. IDENTIFICATION Number E0P 35 ES-0.3 Rev. 1 l Title NATURAL CIRCULATION C00LOOWN WITH STEAM VOID IN VESSEL (WITH RVLMS)
Prepared By H. K. COVIN ,
B. REVIEW 1 have reviewed the above procedure and have found it to be satisfactory.
l TITLE SIGNATURE DATE DEPARTMENT HEAD l
l C. UNREVIEWED SAFETY QUESTION EVALVATION DOCUMENTATION REQUIRED:
(Significant change in procedure method or scope YES [ ] NO [ ]
I as described in FSAR) l (if yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO [ ]
(if yes, document in PORC/50RC meeting minutes)
D. INTEGRATED SAFETY REVIEW REQUIRED (Affects res* .se of Safety Systems, performance YES [ ] NO [ ]
of safety- . sated control systems or performance of control systems which may indirectly affect safety system response.)
(If yes, document in PORC/50RC meeting minutes.)
l E. PROCEDURE REQUIRES (h30RC REVIEW YES N NO [ ]
F. (ORC /SORC APPROVAL .
h/50RCMeetingNumber 3*b7'*2dl G. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
' Y Q A Station /5ergice/ Unit Superint#iident Effective Date SF 301 N'V- 7 8810260219 801007 Page 1 of 1 PDR ADOCK 05000213 P PDR l
t
! I i .
1 1
E0P 35 ES-0,3 Page 1 ;
l ,
Rev 1 ,l j
i i' i
i NATURAL CIRCULATION COOLDOWN WITH STEAM V010 IN VESSEL (WITH RVLMS)
(
j
, i-j Pace No. Eff. Rev.
t 1-7 1 J l
i i
O .
k l
l l
I I
l' I l
l l
O :
- l
,1
- NATURAL CIRCULATION COOLDOWN WITH E0P 35 ES-0.3 Page 2 l STEAM VOID IN VESSEL (WIT;I RVLMS) Rev. 1 $
f a
[
- )
o A. PURPOSE i
i This procedure provides actions to continue plant cooldown and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void- l
' in the upper head region with a vessel level system available to l monitor void growth. l J i B. ENTRY CONDITIONS j This procedure is entered from E0P 35 ES-0.2, NATURAL CIRCULATION j C00LDOWN, after completing the first eleven steps. i r
l This procedure was written for Modes 1, 2 and 3 near no load :
i conditions. Using this procedure when not in these modes !
l requires a step by step evaluation to determine if the required I
! action is still applicable to current plant conditions. {
U l i
f
- i
)
i i
j l
l 2
I I
l' b
i i
l l
l VPK44 2 1943 i
. NATURAL CIRCULATION C00LDOWN W11H E0P 35 ES-0.3 Page 3 STEAM VOID IN VESSEL (WITH RVLMS) Rev. 1 :
s ,
\s / i
-- g?IP ACTH)NitXPECTED RESPONSE RESPONSE NOT OSTMNED CAUTION
, 1. If SI actuation occurs during this procedure ECP 35 E-0, REACTOR TRIP OR SATETY INJECTION, should be performed.
- 2. The first eleven steps of E0P 35 ES-0.2, NATURAL CIRCULATION -
COOLDOWN should be performed before continuing with this procedure.
. NOTE
- 1. Foldout page should be open.
- 2. RCPs should be run in order of priority (2,1. THEN 3 or 4) to provide normai PZR spray.
- 3. If conditions can be established for starting an RCP during this procedure Step 1 should be repeated.
- 4. If the computer is not available to measure core exit TCs, manually measure TCs.
(
- 5. If auxiliary spray is required during procedure performance, maintain spray flow and throttle charging flow as necessary for proper plant control.
1 Try to Restart an RCP
- a. Establish conditions for a. Go to Step 2.
starting an 9CP, per OP 3301D, RCP OPERATION
- b. Check RVLMS head Icvel b. Perform the following AED plenam level -- 100%
- 1) Increase PZR level to approximately 90%
using charging and letdown.
i
- 2) Establish subcooling ,
> 70*F by dumping steam to atmosphere t
- c. Start one RCP c. Go to Step 2.
l d. Go to OP 3208. PLANT l C00LD0kN CFkes-1 3 44
1
- i NATURAL CIRCULATION C00LDOWN WITH E0P 35 ES-0.3 Page 4 '
STEAM VOID IN VESSEL (WITH RVLMS) Rev. 1 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINiQ l
NOTE f
Saturated conditions in the P7R should be established before trying to decrease PZR level.
2 Establish PZR Level To Accommodate Void Growth a Place PZH level controls in manual
- b. Check PZR level - b. Control charging and BET %IEN 20% AND 30% letdown as necessary.
3 Continue RCS Cooldown And Initiate Depressurization
- a. Maintain cooldown rat.e in RCS cold legs -
< 100*T/HR
- b. Maintain RCS subcooling (j
xs hased on core exit TCs -
> 50*r
- c. Maintain RCS temperature I and pressure to the right '
of the 60*F/HR curve on Tech Spec figure 3.4-3 i RCS COOLDOWN LIMITATIONS ;
- d. Check letdown - IN SERVICE d. Depressurize RCS using one PZR PORV. Go to Step 4.
5
- e. Depressurire RCS using auxiliary spray O
0 % Va-1 3 44
NATURAL CIRCULATION C00LDOWN WITH E0P 35 ES-0.3 Page 5 STEAM VOID IN VESSEL (WIT}l RVLMS) Rev. 1 0 --
STEP ACTHM0tXPECTED RESPONlt RESPONlt NOT QBTAINED NOTE With a steam void in the vessel head, decreasing PZR pressure will cause the void to expand and PZR level to increase.
4 Control PZR Level
- a. Level - > 20% a. Control charging and .
letdown, as necessary, to increase PZR level to >
20%.
- b. Level - < 90% b. Perform the following
- 1) Turn on PZR heaters to maintain PZR pressure stable.
- 2) Decrease PZR level to
< 90% by one of the following a) Control charging and letdown as necessary.
- OR -
b) Continue cooldown to shrink RCS inventory, 5 Check RVLMS plenum level Repressurize RCS to maintain GREATER TilAN OR EQUAL TO 82% RVLMS GREATER THAN 82%.
Return to Step 3.
6 Check If S1 Accumulators Should Be Isolated
- 4. Check PZR pressure 4. DO NOT Isolate S!
< 1000 psia Accumulators. Continue with Step 7. Vl(EN requirements met, THEN do Step 6b.
- b. Close the St Accumulator b. IF any accumulators Isolation valves and OPEN cannot be isolated THEN
Accumulator Isolation vent off pressure from x_- motor supply breakers appropriate unisolated accumulators CPN661 S S4
NATURAL CIRCULATION C00LDOWN WITH E0P 35 ES-0.3 Page 6 STEAM VOID IN VESSEL (k'ITH RVLMS) Rev. 1 i
%)
STEP ACTION. EXPECTED RESPONSE RESPON$t NOT OBTAINED 7 Maintain Letdown Flow
- a. Open letdown orifice isolatier. valves as necessary
- b. Adjust low pressure letdown control valve setpoint as necessary 8 Maintain RCP Seal Injection Flow between 8 to 13 spm 9 Check if RHR System Can Be Placed in Service
- a. RCS temperature - a. Return to Step 3.
< 350*F
- b. RCS pressure - b. Return to Step 3. '
< 390 PSIA
- c. Place RHR System in service
~ as follows:
- 1. OP 3310A, RESIDUAL HEAT REMOVAL SYSTEM
- 2. OP 3208 PLANT COOLDokN
- d. Disable all but one chargint pump and as least one SI pump prior to cooling down to < 350*F
- e. Arm cold overpressure protection system 10 Continue RCS Cooldown To Cold Shutdown O
.m . , . .
e NATURAL CIRCULATION C00LDOWN WITH E0P 35 ES-0.3 Page 7 STEAM VOID IN VESSEL (WITH RVLMS) Rev. 1 U)
- STEP ACTION,tXPECTED RESPONSE RESPONSE NOT OSTAINED 11 Continue Cooldown Of Inactive Portion of RCS '
t
- a. Cool upper head region 1. IF the head cannot be ,
using CRDM fans cooled by CRDM fans THEN '
use vessel head vent excess letdown,
- b. Cool SG U-tubes by dumping ;
steam from all SGs [
- c. RVLMS head and plenum c. Return to Step 10.
level - 100%
CAUTION !
Depressurizing the RCS before the entire RCS is
< 200*F may result in additional void formati e in the RCS. i O 12 Determine If RCS Depressurization Is Permitted
- a. Entire RCS AND RVLMS a. DO NOT DEPRES5URIZE RCS.
Head T/C's LESS THAN Retur;,to Ctep 10, 200*F
- b. Go to OP 3208, PLANT C00LDOWN FINAL ,
e_ , ..
I
-. _ , _ _ _ _ _,