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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:Operating Procedures
[Table view] |
Text
NRC FORM 195 pl U.s. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER 12.7GI ~ i FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAl DATE OF DOCUMENT Mr Ziemann Florida Power & Light Co LL Miami, Fla Hhrig DATE RECEIVED R E ]2 ]e /6 HLETTE R IZIf4OTOB IZED f'ROP INPUT FORM NUMBER OF COPIFS RECEIVED S ORIGINAL RUNG LASS IF I E D one signed DCOPV DESCRIPTION ENCLOSURE Ltr trans the following: "Steam Generator Feedwater Hammer Test"......
(40 cy encl rec'd)
St Lucie $P1 ACKNOWLm~GPD PLANT NAtIE>>
DOMO'ZMOVZ SAFETY FOR ACTION/INFO RMATION 12<<14-76 ehf ASSXGNED g):
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LXC ASST LIC ASST INTERNAL D IST RI BUTION REG FILE SYSTEMS SAFETY PLANT SYSTEMS SITE SAFE NRC R HEINEMAN TEDESCO SCHROEDER ~OA OELD GOSSXCK & STAFF ENGINEERING IPPOLITO EI MXPC MACARRY ERNST CASE KNIGHT BALLARD HANAUER SXHWEXL OPERATING REACTORS SPANGLER HARLESS PA[lL CK STELLO SXTE TECH PROJECT MANAGEMENT REACTOR SAFE OPERATING TECH GAMMXLL BOYD ROSS EISENHUT STEPP PE COLLINS HULMAN HOUSTON ROSZTOCZY PETERSON CHECK SXTE ANALYSIS MELTZ VOLLEY IER HELTEMES AT & I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KREGER EXTERNAL DISTR I BUTION CONTROL NUh1 BE R LPDR f ~c.c c ~ NAT LAB BI~OO~h Q'LR TXC: REG AXE KSON OR NSXC: LA PDR ASLB: CON ULTANTS:
ACRS CYS -NQRB&Q/ T S NBC FORM 195 (2 7G) 5 0
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@ )ggy FLORIDA POWER & LIGHT COMPANY December 7, 1976 l L-76-415 Office of Nuclear Reactor Regula I 6 ~<<ufo Attn: Dennis L. Ziemann, Chief I1RC Operating Reactors Branc ' 'Qgpa Division o f Operating Re c r@QQ 1 O 3 S. Nuclear Regulatory Commiss'~ma<<~ ~~10'.
Washington, D.C. 20555
Dear Mr Ziemann:
Ch Re: St. Lucie Unit No. 1 Docket No. 50-335 Operating License DPR-67 Enclosure 1 Item C.l Enclosed'.herewith for your review is a copy of the St. Lucie Plant Unit No. 1 Preoperational Test Procedure No. 0700080B,"Steam Generator Feed-water Hammer Test," which we plan to perform to satisfy the subject license condition. This test procedure was informally given to members of your staff on November 19, 1976.
It is our understanding that members of your staff wish to witness the per-formance of this test. Florida Power 6 Light Company prefers to conduct this test following an unscheduled trip from greater than thirty percent of full rated power for the following reasons:
- 1) the remaining scheduled trips during the power ascension test pro-gram are not compatible with the conduct of this test,
- 2) a trip scheduled specifically to perform this test would cost Florida Power & Light Company customers approximately $ 58,000.
The NRC will be notified at least two days before the plant conditions are such that this test could be performed so that appropriate plans may be made for witnessing the test.
The final procedure as implemented may reflect minor revisions ma'de in accord-ance with St. Lucie Technical Specifications. Any such changes will not, how-ever, alter the intent of the test.
Our present schedule indicates that we could be ready to perform the attached test as early as December 14th, 1976. We, therefore, request any comments PEOPLE... SERVING PEOPLE
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To: Dennis L. Ziemann December 7, 1976 Re: St. Lucie Unit No. 2 Page Operating License DPR-67 which you may have on either the attached procedure or plans for its per-formance prior to December 12, 1976, so that any such comments might be factored into our plans.
Yours very truly, Robert E. Uhrig Vice President REU/ls Encl.
cc: Norman C. Moseley, Region II Robert Lowenstein, Esq.
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Page 2 of 8 I
PREOPE~NAL TEST PROCEDURE No. 07000 STEAl~i GENERATOR FEEDHATER HA~Q'1ER TEST i Revision l 0
5.0 Instrumentation
The following parameters shall be monitored and/or recorded 'during the test. (S/G 1B level and Aux FWP flow to S/G 1B shall be con-tinuously recorded during steps 12.2 thru 12.3.
NOTE: Aux H~P flow will probably be pegged high at 300 gpm.
Aux H6'A & 1B Amperage (Record while feeding up)
Pzr Pressure ~ - S/G 1A & 1B Level Pzr Level S/G lA & 1B Pressure Loop 1A & lB Hot Leg Temp. Aux BG'low to,S/G 1B Loop 1A & 1B Cold Leg Temp. Aux H6'ressure:.
Loose Parts llonitor (if in service).
6.0 Related System Status:
6.1 Atmospheric steam dump and SBCS are operational.
Verified by Date 7.0 ecial Haterials or E ui ment: ) ' 2 S ~ I 7.1 Temporary recorders (as necessary) 8.0 Tem orar Connections:
'Pomnorarlr recorders'ay bq conrlpcted Section 5.0 in addition to installed recorders/indicators; --
~ Le 9.0 Precautions & Limits:
9.1 The test shall be aborted if S/G level is off scale. Recovery shall be made in accordance with EP 0700040, Loss of Feedwater or Steam Generator Level.
9.2 The test shall be aborted if RCS cooldown is excessive.. Co'oX-down shall not exceed 75F/hr. The test shall be aborted of Pzr level reaches 27%.
9.3 The fourth 'RCP shall be secured below 510F (Tcold).
9.4 The preferred mode of adding feedwater during the feedup test is via motor driven Aux H6'o minimize heat removal from the RCS.
9.5 If SBCS is used for temperature control during the hold period, I-HCV-08-IB shall be closed to minimize level decrease in S/G 1B The setpoint of I-HCV-08-2B shall be raised to 920 psig in auto.
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. 0 PREOPERATIONAL TEST PROCEDURE No. 07000808, STEA".1 GENERATOR FEED'HATER HAKER TEST
- 9. 0 (cont) 9.6 Only persons authorized by the Test Director and/or Nuclear Plant Supervisor are allowed in containment.
10.0 Acce tance Criteria:
10.1 The test is complete upon successful completion of steps 12.2 and 12.3 with no audible or visual indications of damagi>>
Feedwater hammer.
11.0 Records Re uired:
11.1 The completed copy of this procedure with applicable recorder traces shall be filed in accordance with QI 17-PR/PSL-l.
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- PREOPERA NAL TEST PROCEDURE- NO. 070008 Rev. 1 STER'I GENERATOR FEEDS'ATER 1bQL1ER TES
- 12. 0 Detailed Instructions:
12 ' Initi.al Setup & Steamdown 12.1.1Comm nce raising'Pressurizer level to at least 45%.
Charging pump high level override bypass may be used to allow running 2 charging. pumps i.f desired. Mhen level is at 45%, switch to Backup RRS. This step shall be completed by 12.3,4. Proceed with 12.1.2-12.3,3 12.1. 2 concurrently.
Verified by 'ate Transfer control of S/G 1B pressure 'from the SBCS
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to the atmospheric dump by placi.ng the I-HCV-08-2B controller setpoin't to the existing S/G pressure in auto and closing I-HCV-08-1B. Verify that the atmospheric dump opens and that pressure- is being controlled by it.
Time of trip . Pre-trip Power level Verified by Date 12.1.3 Raise the pressure setpoint for I-HCV-08-2A. to 920-
, psig. Raise the pressure setpoint on SBCS to 930 t
psia. Maintain water level in S/G lA by reducing e
feed flow.
Verified by a
Date n
- 12. 1;4 Reduce the level in S/G 1B by discontinuing feed to that generator and by maintaining its pressure at 900 psia.
Verified by Date 12.1 ~ 5 Note the time that S/G 1B level drops below 34 '% .
(Bottom of Beadvater Thermal Sleeves) .
Time Verified by Date
- 12. 1 e6 Note the time that S/G 1B level reaches 29%.
Time Verified by Date
- 12. 1.7 Verify Blowdown is secured from'S/G 1B.
Verified by Date 12.2 Hold Period (2 hrs. or 5% Level) 12.2 ~ 1 Vhen S/G 1B level has dropped to between 27% & 29%,
reduce the setpoint on SBCS to 900 ps%a and increase'
Page 5 of 8
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PREOPERATIONAL TEST PROCEDURE NO. 0700080B, Rev. 1 STEQl GENERATOR FEED'HATER 1hQMER TEST 12.0 (cont) 12.2 (cont) 12.2.1 (cont) the setpoint for I-HCV-08-2B to 920 psig. Verify that steam flow from S/G 1B atmospheric dump has decreased.
Verified by Date I = 4 p 12.2.2 Feed S/G IA as necessary to maintain a level of 65%.to 70%. Verify the RCS .temperature is con-trolled by S/G IA.
Verified by Date 12.2.3 Near the end of the hold period, verify an observer is stationed in the area of the Aux FtG'nd that "
communications are established with the control room.
Verified by Date 12.2.4 Hear the end of the hold period, perform the following:
.All Pzr backup htrs ON P'I $ P2 Pzr heaters Q'hf Verify Pzr pressure controlling via Pzr spray. Pzr pressure setpoint may have to be adjusted .to maintain 2250 psia.
Verified by Date NOTE: If S/G IB level approaches 5%, immediately .
proceed to step 12.3.
12.3 Feedup Test a
12.3.1 'Verify that 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> have passed since the time recorded in step'12.1.5 ~or that S/G IB level is at 5%. Record the timt Verified by Date 12.3.2 Verify there has been no feedwater addition to S/G 18 during the above time interval.
Verified by Date 12.3.3 Secure Blowdown from S/G IA.
Verified by Date
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PREOPERATIONAL TEST PROCEDURE No, 07000808,
. ~ Rev. 1 STEAN GELlERATOR FEED'hATER HsQQ'ER TEST 12.0 (cont) 12.3 (cont) ft 12.3.4 Station an observer inside the personnel airlock with the inner door open a few inches to listen for PM hammer. Using two motor driven Aux HK's, iniate feedwater flow to S/G 1B in accordance with OP 0700022 (perform steps 8.2.2 and 8.2.5 concurrently.)
Establish as close to maximum flow (all valves in Aux H4 flow path. to S/G 1B open) as cooldown rates allow.
If cooldovn rates appear excessive, make small 're-ductions in Aux H6'lov.
I NOTE: Aux Pv header flov indication only goes to 300 gpm -use amperage to estimate flow. Since experience indicates cooldown rate will not be a problem, it is expected that we will have maximum flow from the two motor driven Aux FHP's.
Verified by Date
'ate 12;3.5 Increase level in S/G 1B to greater than43~ while maintaining feedvater flow at the above established Qbsel ¹>>s sh 1 3 eco d thci>> ob,e ticns QQ the su~mary sheet. Record lA & lB AKf pump amperage on summary sheet.
Verified by 12.4 System Restoration 12.4.1 Reduce feedwater flow to S/G 1B to desired amount to minimize RCS cooldovn. Mhen S/G 1B level is above .
50K, setpoints for SBCS and both atmospheric dump controllers (I-HCV-08-2A & I-HCV-08-2B) may be Reset to 'nornel no-load conditions. I-HCU-08-1B may be opened. 5faintain norrwl hot shutdown steam generator.
levels.
Verified by Date 12.4.2 Regain normal control of Pzr pressure.
Verified by 12.4.3 Initiate Blowdovn from S/G 1A, and S/G 1E.
Verified by Date 12.4.5 Collect all data, recording charts and document observations of personnel.
Verified by Date
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a 1) p PREOPER XONAL TEST PROCEDURE Yo. 07000, Rev. 1 STEPu~f GENERATOR PEED'HATER HA~a&ER TEST 13.0 Deviatioris:
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t Page 8 of 8 REVISION 1, PREOPERATIONAL TEST PROCEDURE HO, .07000SOB r
PREOPERATIONAL TEST SENARY REHARKS
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