ML20072L977
| ML20072L977 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/25/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20072L980 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.1, TASK-TM 3F-0383-31, 3F-383-31, NUDOCS 8304010091 | |
| Download: ML20072L977 (5) | |
Text
Power C o a P o a a t s o se March 25,1983 3F-0333-31 Director of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, item I.C.1 Guidance for the Evaluation and Development of Procedures for Transients and Accidents
Dear Mr. Eisenhut:
Florida Power Corporation (FPC) is proceeding with the implementation of the upgraded emergency procedures required by the subject item in NUREG-0737, Supplement 1. As part of that implementation, FPC is required to submit a Procedures Generation Package.
The Procedures Generation Package consists of the below listed items and represents FPC's response to Section 7.1 of Supplement I to NUREG-0737.
o Abnormal Transient Operator Guidelines (ATOG) for Crystal River Unit 3 o Writers Guide for Abnormal, Verification, and Emergency Procedures for Crystal River Unit 3.
o Validation Program Description o Training Program Description LoVl f
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g',5 L.#'f 8304010091 830325 i PDR ADOCK 05000302 P PDR General Office 32o1 Thirty-fourth Street South e P O. Box 14042. St. Petersburg, Flor:da 33733 e 813-866-5151
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March 25,1983 3F-0383-31 Page 2 In order to implement the upgraded emergency procedures at the start-up from the current refueling outage, we request a waiver from the three (3) month NRC review period between submittal of the Procedure Generation Package and commencement of training. Please inform FPC as to the determination on the waiver request by May 2, 1983, so training may begin in early May with final placement of the upgraded procedure in the Control Room occurring in early July at the completion of the current refueling outage.
Sincerely,
/
G. R. Westafer Manager Nuclear Licensing and Fuel Management WM3:mm cc: Mr. 3. P. O'Reilly Regional Administrator, Region 11 Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30303 1
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UPGRADED EMERGENCY PROCEDURE VALIDATION PROGRAM 1.0 GENERAL The purpose of the Validation Program is to demonstrate the usability of emergency procedures. The instructions to operators must be as follows:
o Complete o Understandable e Compatable with conditions.
2.0 PROGRAM DESCRIPTION The following items were evaluated during development of the Validation Program, o Validation Methods e Facilities e Evaluation Criteria e Documentation The testing will be accomplished as follows:
e Walkthrough Validation at the Crystal River Facility e Simulator Validation at the B&W Training Facility in Lynchburg, VA.
3.0 IMPLEMENTATION Validation of procedures will be a long term process following operator training on the Upgraded Emergency Procedures. Simulator validation will be accomplished during operator requalification training sessions. Only those procedures compatible with the Lynchburg Facility will be tested by simulation.
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UPGRADED EMERGENCY PROCEDURE TRAINING PROGRAM 1.0 GENERAL The training program to support implementation of Crystal River 3 Upgraded Emergency Procedures is presented in this section.
2.0 PROGRAM CONSIDERATIONS The following major items were considered during development of the training program:
e Training method to be used e Training and outage activities schedule and constraints e Knowledge level of instruction (RO or SRO) e Extent of procedure content change o Extent of procedure format and philosophy change 3.0 PROGRAM GOALS The overall goals embodied in this program are:
o Complete the training and implement upgraded emergency procedures by end of 1983 Refueling Outage, currently scheduled for early July.
e Enable operators to understand the philosophy and structure of the emergency precedure.
e Enable operator to have a working knowledge of the emergency procedures.
4.0 PROGRAM DESCRIPTION The Upgraded Emergency Procedure Training Program has been established to instruct licensed operation, Shift Supervisors, Shift Technical Advisors, and Back-up license holders in the upgraded emergency procedures.
The program consists of classroom instruction in a table-top walkthrough seminar format. The instructions will be taught / discussed on the SRO Level.
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Included in this instruction are the following:
e Regulatory history and philosophy behind the procedure development. This
- includes the human factor model developed by Florida Power Corporation.
e Abnormal procedure which are the first steps in the emergency procedure network.
e Verification procedures which are a proceduralized independent check of critical safety functions in the procedure network.
e' Emergency procedures which are the final set of operator guidelines.
This program is limited to initial training on the upgraded emergency procedures.
Training on procedure revisions and in real time situations will be conducted according to Florida Power Corporation existing methods. These methods include on-shift briefings, required reading and requalification program.
5.0 EVALUATION Testing of operator knowledge will be conducted to ascertain each individuals procedural knowledge.
Validation of the Upgraded Procedure and Operation use thereof is discussed in the previous section.
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8ABCOCK & WILCOX NUCLE AR POWER GENERATION DtvlSON TECHNICAL DOCUMENT l
CRYSTAL RIVER NUCLEAR POWER STATION l UNIT 3 l
ABNORMAL TRANSIENT OPERATING GUIDELINES I
PART I CAUTION I
ATOG Part II Must Be Read and Understood l
Prior to Review or Use of Part I.
1 74-1126473-00 Doc. ID - Serial No., Revision No.
for FLORIDA POWER CORPORATION by BABCOCK & WILCOX s
THIS DOCUMENT WAS PREPARED FOR FLORIDA POWER CORPORATION UNDER MASTER SERVICE CONTRACT No. 582-7087 (B&W No. 582-7108). ANY USE OF THE INFORMATION CONTAINED HEREIN OTHER THAN UNDER THE EXPRESS CONDITIONS OF SAID CONTRACT IS EXPRESSLY PROHIBITED WITHOUT THE WRITTEN PERMISSION OF THE BABCOCK & WILCOX COMPANY.
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BABCOCK & WILCOX l NUCLEAR POWER GENERATION Division NUMBER I RECORD OF REVISION 74-1126473-00 REV. NO. CHANGE SECT / PARA. DESCRIPTION / CHANGE AUTHORIZATION 00 Original Issue - J. J. Kelly Systems Engineering S
Prepared By M Date A/#// [, / hD Reviewed By Date NW / /9h A Approved By 30 Date //- 67 8 1 Approved By jO Date //[f/'fL Released By
,/ Date // 8/8L c,. A r */ . .
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DATE: 10-1-82 PAGE 2
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BABCOCK & WILCOX . . . . , j mactean rowen GENMADON DIYl$lON TECHNICAL DOCUMENT 74-1 26473-00 l TABLE OF CONTENTS 1
1 TITLE TAB NAME SECTION l
Abbrevation Glossary Immediate Action REACTOR TRIP l
['~'\ Section I Section II Vital System Status Verification REACTOR TRIP Section III A Lack of Adequate Subcooling Margin SUBC00 LING Lack of Heat Transfer LACK OF HEAT Section III B TRANSFER l
Excessive Heat Transfer EXCESSIVE HEAT Section III C TRANSFER Section III D Steam Generator Tube Rupture SGTR
% 000LDOWN CP-101 A Large LOCA Has Occurred and the Core Flood Tanks Are Emptying CP-102 Normal Cooldown CP-103 Transient Termination Following an Occurrence That Leaves the RCS .
Saturated With OTSGs Removing Heat CP-014 Transient Termination Following an Occurrence That Leaves the RCS Being Cooled by MU/HPI Cooling CP-105 Transient Termination Following an Occurrence That May Require Pres-surizer Recovery or Solid Plant Cooldown with SGs Removing Heat and RCS Subcooled Specific Rule 1 SPECIFIC RULES Specific Rules Specific Rule 2 Specific Rule 3 Specific Rule 4 SAD SAD Inadequate Core Cooling ICC Section ICC DATE: 10-15-82 PAGE 3
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! BABCOCK & WILCOX NU"8IE NUCitA* POWER GENER ADON OmSION
- TECHNICAL DOCUMENT 74-1126473-00 '
4 VOLUME 1 PROCEDURAL GUIDELINES 1
i List of Figures
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r II Vital System Status Verficiation f III A Lack of Adequate Subcooling Margin i III B Lack of Heat Transfer !
s III C Excessive Heat Transfer ,
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III D Steam Generator Tube Rupture 1 HPI Flow Vs. RC Pressure l
l 2 RC Presure/ Temperature Limits Core Exit Fluid Temperature For ;
3 Inadequate Core Cooling >
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NUCLEAR POWER OtNERATION DIVillON 74-1126473-00
. TECHNICAL DOCUMENT t
, ABBREVIATION GLOSSARY
! ADV Atmospheric Dump Valve AP Abnormal Procedure BWST Borated Water Storage Tank CFT Core Flood Tank CP Cooldown Procedure .
i DHRS Decay Heat Removal System EFP Emergency Feed Pump EFPT Emergency Feed Pump Turbine EFW Emergency Feedwater EP Emergency Procedure ES Engineered Safeguards I
i ESAS Engineered Safeguards Actuation System FW Feedwater 3
HPI High Pressure Injection ICC Inadequate Core Cooling ICS Integrated Control System LOCA Loss of Coolant Accident l LPI Low Pressure Injection i MFPT Main Feed Pump Turbine MFW Main Feedwater j MSIV Main Steam Isolation Valve
! MSR Moisture Seprator and Reheaters MSSV Main Stean Safety Valve NaOH Sodium Hydroxide N2 Nitrogen NI Non-Nuclear Instrumentation NR Narrow Range NSCCW Nuclear Services Closed Cycle Water OP Operating Procedure PORV Pilot Operated Releief Valve l P-T Pressure vs. Temperature Plot for Reactor Coolant DATE: 10-1-82 PAGE 4
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! NUCLEAR POWER GENERATION DIY1550N
! 74-1 26473-00 TECHNICAL DOCUMENT ,
PZR Presurizer i
j RB Reactor Building -
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! RC Reactor Coolant 4
RCP Reactor Coolant Pump f RCS Reactor Coolant System !
RTD Resistance Temperature Detector RV Reactor Vessel l SAD System Auxiliary Diagram SG Steam Generator l SGTR Stean Generator Tube Rupture SLBIS Steam Line Break Instrumentation System l SU Startup TBV Turbine Bypass Valve !
i j T/C Thennocou ple !
i T hot Reactor Coolant Hot Leg Temperature T sat Saturation Temperature WR Wide Range l
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t l -BWNP-20007 (6-76) 1 SABCOCK & WILCOX I NucttAA POwet GENERATION OlVIStON 74-11264 U-00.
TECHNICAL DOCUMENT 1
Section I l t
! IMMEDIATE ACTIONS :
I j Determine whether this is a reactor trip or a forced shutdown situation !
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and proceed below, i
f l Reactor Trip Forced Shutdown
- a. Verify the reactor trip, a. IF a SG tube rupture has occurred E indicated by main steam line, i
- b. Verify the turbine trip, auxiliary and fuel handling
} building exhaust duct (RM-A2),
- c. Go to Section III. auxiliary building vent exhaust i duct (RM-A4), and/or condenser vaccum pump (RM-A12) radiation j monitoring alarms, THEN go to j Section III D.
J j b. IF a forced shutdown is required l 5 technical specifications or by
' other operating documents, THEN ,
shutdown plant to required con-j ditions per normal procedures, l starting with OP-204, " Power ,
1 Ope ra t ion." Continue with Sec-tion II as soon as the reactor is shutdown.
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I Section I DATE: 10-1-82 PAGE 6 e - vr vrr -Sw- + w-e ew -se,e r a- e+ w -wnw s e m _
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l BABCOCK & NVILCO.X NUCLEAR POWER GENERADON DIV1510N 74-1126473-00 ;
TECHNICAL DOCUMENT Section II VITAL SYSTEM STATUS VERIFICATION Verification Column Remedial Action Column VERIFY THE FOLLOWING IF VERIFICATI00N CANNOT BE MADE, PERFORM THE FOLLOWING:
1.0 REACTOR POWER DECREASING ON Start HPI from BWST.
INTERMEDIATE RANCE.
2.0 ALL RODS ON BOTTOM. Begin emergency boration as neces-
sary. Borate to a 1% shutdown mar-margin.
3.0 ALL MAIN TURBINE STOP VALVES Close M3IVs (MSV-411, -412, -413, SHUT. -414) and trip turbine from front standard.
4.0 FEEDWATER RAS RUNBACK. Trip running feedwater pumps.
AND SG LEVELS ARE DECREASING. Verify EFW starts.
5.0 CROSS-TIE VALVE RAS OPENED. a. Open FW Cross-tie valve (FWV-28).
- b. ))[ crosstie cannot be opened ,
THEN start and verify EFW to affected SG.
6.0 LETDOWN FLOW THROUGH BLOCK Close letdown block orifice bypass ORIFICE ONLY valve (MUV-51).
Section II DATE: PAGE 7 10-1-82
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l BWNP-20007 (6-76) l BABCOCK & WILCOX wu sen
\ wucteAn Powea oewenAtow onnscw 74-1126473-00 TECHNICAL DOCUMENT i
Verification Column Remedial Action Column i
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VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
7.0 NNI/ICS POWER ON. Continue at Step 7.1 (Go to Step 8.0) 1 7.1 NNI POWER ON. All NNI(x) and NNI(y) Power Lost (otherwise go to Step 7.2).
- a. Trip both MFW pumps,
- b. Trigi all but one running RCP.
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- c. Trip both EFW pumps,
- e. Verify subcooling margin by mon-itoring RCS preasure on the ES board and monitoring incore i temperatures. E subcooling margin is lost, THEN trip the remaining RCP.
( f. Continue HPI cooling until at least one channel of NNI in-strumentation is restored. Go to Step 8.0 and complete the vital systems status check. E no additional abnormal conditions
- exist, THEN go to CP-105.
J Section II DATE: 10-1-82 PAGE 8
BWNP-20007 (6-76)
BABCOCK & WILCOX NUMBER NUCLEAR POWER GENERATION DIY1510N TECHNICAL DOCUMENT 74-1126473-00 Verification Column Remedial Action Cclumn VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
7.2 ICS POWER ON. All ICS Power Lost (Otherwise go to Step 7.3).
EFW is not available, THEN go to Step 7.2.b. OTHERWISE continue at Step 7.2.c.
- b. Trip all but one running RCP and establish HPI cooling. Il[sub-cooling margin is lost, THEN trip the remaining RCP. Go to Step 8.0 and complete the vital systems status check. IF no additional abnormal can'ditions exist, THEN go to CP-105.
- c. Close EFW block valves (FWV-34 and FWV-35) .
- f. F any NNI(x) or NNI(y) power is lost concurrent with loss of all ICS power, THEN monitor plant condition using alterna-tive instrumentation. If neces-sary, control SG pressure with ADV(s).
Section II DATE: 10-1-82 PAGE 9
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BABCOCK & WILCOX ER NUCLEAR POwtR GENESATION OlVISION TECHNICAL DOCUMENT 74-1126473-00 Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
7.2 ICS POWER ON. (Cont'd) g. Continue with Step 8.0 and com-plete the vital systems statua check.
1 IF power to ICS/NNI cannot be restored , THEN station manage-ment needs to decide whether or not a cooldown is required .
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BABCOCK & WILCOX NUCLEAR POWER GENERATION DIVI $lON 74- 126473-00 TECHNICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE,FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
E' 7.3 NNI(X) POWER ON. All NNI(x) Power lost (Otherwise go to Step 7.4).
- a. Start EW to SG "A" through EFW bypass valve (FWV-162) and con-trol level at 30 inches. Con-trol SG "A" pressure with ADV.
IF EFW is unavailable, THEN Eintain primary to secondary heat trans fer solely with SG "B".
- b. Monitor plant condition using alternative instrumentation.
- c. Maintain PZR level with make-up control valve (MUV-31).
- d. Continue with Step 8.0 and com-plete the vital systems status check. F power to NNI(x) can-not be restored, THEN station management needs to decide whether or not a cooldown is required.
O Section II DATE: 10-1-82 PAGE 11 1
BWNP-20007 (6-76) d BABCOCK & WILCOX Numeen NucteAn powen GENERATION oIVl5 TON 74- 26473-00 TECHNICAL DOCUMENT
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Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, v PERFORM THE FOLLOWING:
7.4 NNI(Y) POWER ON. All NNI(y) Power Lost (Otherwise go to Step 7.5).
trol level at 30 inches. Con-trol SG "B" pressure with ADV.
IF EFW is unavailable, THEN main-tain primary to secondary heat transfer. solely with SG "A".
- b. Monitor plant conditions using alternative instrumentation.
- c. Maintain PZR level with make-up control valve (MUV-31).
- d. Place condensate pump control-1ers in " hand". Disconnect analog memory module 6-7-8Y and 6-7-10Y. Reconnect modules after NNI power is restored.
- e. Continue with Step 8.0 and com-plete the vital systems status check. F power to NNI(y) cen-not be restored , THEN station management needs to decide whether or not a cooldown is required.
Section II DATE: 10-1-82 PAGE 12
BWNP-20007 (6-76)
BABCOCK & WILCOX NuusEn NUCLEAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74-1126473-00 Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
7.5 NO PARTIAL LOSS OF NNI/ICS Partial Loss of NNI(x), NNI(y), or POWER. ICS Power. (Otherwise go to Step 8.0).
- a. Maintain plant control using alternative controls and in-strumentation. Continue with Step 8.0 and complete the vital systems status check. F lost power cannot be restored, THEN station management needs to decide whether or not a cool-down is required.
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Section II DATE: 10-1-82 PAGE 13
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I BABCOCK & WILCOX OIE NUCLEAR POWER GENERATON DIVI $CN 74-1126473-00 TECHNICAL DOCMENT Verification Column Remedial Action Column i VERIFY THE FOLL0k'ING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
8.0 0FFSITE POWER AVAILABLE. a. Start or verify auto start and
, loading of diesel generators.
3 E onsite power is unavailable,
, THEN manually transfer to Unit 1
& 2.
, b. With EFW properly throttled, l raise SG 1evel to 50% on the operate range.
- c. Ensure a' makeup pump is restarted
, and RCP seal injection reestab-
- lished. -
- d. Start diesel driven air com-pre s so r .
- e. Manually load pressurizer heaters.
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BABCOCK & WILCOX NussEt NUCLEAR POWER GENERATION DIVISION 74-1126473-00 TECHNICAL DOCUMENT Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
9.0 RCS PRESSURE GREATER THAN 1500 PSIG ALARM 1500 PSIG AND a. Verify HPI and LPI channels have RB PRESSURE LESS THAN 4 actuated by noting the indicating PSIG (NO ESAS ALARMS). lamps on the ES panels ES(A),
ES( AB) , and ES(3) . IF the HPI/
LPI system is not operating pro-perly, THEN refer to the SAD sec-tion.
- b. Close makeup tank outlet valve (MU-64).
- c. Close PORV block valve (RCV-ll).
- d. IF subcooling margin is lost, THEN Immediately trip all RCPs. While properly throttling feedwater, raise SG levels to 90-95% on the operate range.
- e. IF loss of of fsite power occurs lEid " Diesel Gen, in 30 Min.
Rating" alarm actuates, THEN power must be supplied by Unit I and II within 30 minutes to prevent loss of motor-driven EFP.
O Section II DATE: PAGE 10-1-82 15
BWNP-20007 (6-76) 8ABCOCK & WILCOX Numsen NUCLEAR POWER GENERATION DIYlSloN 74- 126473-00 O TECHNICAL DOCUMENT o
Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE,
( PERFORM THE FOLLOWING:
4 PSIG ALARM
- a. Verify HPI, LPI and reactor build-ing isolation / cooling channels have actuated by noting the indi-cating lamps on the ES panels ES(A), ES(AB), and ES(B). IF the HPI/LPI system is not oW rat-ing properly, THEN refer to the SAD section.
- b. Close makeup tank outlet valve (MUV-64),
- c. Close PORV block valve (RCV-ll).
l d. Verify or reestablish RCP seal injection and NSCCW flow.
- e. Verify NaOH valves are open (BSV-36 and BSV-37).
30 PSIG ALARM
- a. Verify proper RB spray flow:
IF a high flow alarm occurs, T1700 gpm), THEN throttle RB spray to 1500 gpm.
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Section II DATE: 10-1-82 PAGE 16
BWNP-20007 (6-76)
BABCOCK & WILCOX NUC; EAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74-1126473-00 Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
10.0 NO SLBIS ACTUATION. "A" Actuation Verify the following valves closed:
MSIV, MSV-411, MSIV, MSV-412, j MFW Block Valve, FWV-30, Lo Load Block Valve, FWV-31, SU FW Block Valve, FWV-36, EFW to Upper Nozzle, FWV-35, EFW Byapss Valve , FW-162, FW Pump Discharge Cross-tie Valve, FWV-28, FWP-2A Suction Valve, FWV-14, "B" Actuation Verify the follawing valves closed:
MSIV, MSV-413, MSIV, MSV-414, MFW Block Valve, FWV-29, l Lo Load Block Valve, FWV-32, ,
SU FW Block Valve, FWV-33, l EFW to Upper Nozzle, FWV-34, EFW Bypass Valve, FWV-161, FW Pump Discharge Cross-tie Valve, FWV-28, l FWP-2B Suction Valve, FWV-15, i l
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Section II DATE: 10-1-82 PAGE 17 I I
e BWNP-20007 (6-76)
BABCOCK & WILCOX NumsER NUCLEAR POWER GENERATION DIVI $ ION
\ TECHNICAL DOCUMENT 74-1126473-00 Verification Column Remedial Action Column VERIFY THE FOLLOWING: IF VERIFICATION CANNOT BE MADE, PERFORM THE FOLLOWING:
11.0 ADEQUATE SUBC00 LING Go to Lack of Adequate Subcooling MARGIN EXISTS Margin,Section III A.
12.0 PROPER PRIMARY TO a. IF a lack of heat transfer SECONDARY HEAT TRANSFER Eists, THEN go to Lack of EXISTS. Heat Transfer,Section III B.
\ b. IF excessive heat trans fer Hists, THEN go to Excessive Heat Transfer,Section III C.
13.0 NO MAIN STEAM LINE OR Go to SGTR Section III D.
CONDENSER VACUUM PUMP RADIATION MONITOR ALARMS.
14.0 THE PLANT IS STABLE IN A SAFE SUBC00 LED CONDITION WITH PROPER PRIMARY TO
~ SECONDARY HEAT TRANSFER AND NO MAJOR PRIMARY BOUNDARY FAILURES. FURTHER I ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
Section II DATE: 10-1-82 PAGE 18
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BABCOCK & WILCOX NUMSER NUCLEAR POwen GENERATON DIVISCN 74-1126473-00 TECNNICAL DOCUMENT III A LACK OF ADEQUATE SUBC00 LING MARGIN r
FOLLOWUP ACTIONS FOR TREATMENT OF LACK OF ADEQUATE SUBC00 LING MARGIN 1.0 TRIP ALL RCPs.
! 2.0 INITIATE HPI.
2.1 See Specific Rule 1.0.
3.0 ISOLATE POSSIBLE LEAKS.
3.1 Close the PORV block valve (RCV-11).
i 3.2 Close letdown isolation valve (MUV-49).
3.3 Close the PZR spray block valve (RCV-13).
3.4- Verify closed DHRS drop line valve (DHV-1),
i 3.5 Verify closed RCP seal return valve (MUV-253).
i l 4.0 ELIMINATE EXCESSIVE HEAT TRANSFER, IF IT EXISTS.
4.1 If Excessive heat transfer exists, then go to III C and l continue III C until the excessive heat trans fer is terminated. Otherwise continue with Step 5.0.
5.0 MAINTAIN PROPER SG LEVELS.
1 5.1 Raise SG 1evels to 90-95% on the operate range while pro-perly throttling main or emergency FW through the EFW nozzles. (see Specific Rule 3.0).
6.0 E SUBC00 LING MARGIN HAS BEEN ESTABLISHED, THEN GO TO STEP 10.0 OTHERWISE CONTINUE.
I e
4
, Section III A DATE: 10-1-82 PAGE 9
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BABCOCK & WILCOX go,,,,
NUCLEAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74-1126473-00 7.0 g SUPERHEATED, THEN GO TO SECTION ICC. OTHERWISE CONTINUE.
7.1 g at any time during the transient incere T/C tempera-tures indicate superheated conditions based on the satura-tion curve of Figure 3, THEN go to Section ICC. OTHERWISE continue at Step 8.0.
8.0 IF_ THE CFTs HAVE EMPTIED, THEN GO TO CP-101. OTHERWISE CONTINUE.
S The core flood tanks emptying is an indication of a major T LOCA, CP-101 provides instructions for long-term core cool-A ing following a major LOCA. Do not go to Section III B.
T Primary to secondary heat transfer will be lost and cannot U be regained.
S 9.0 IF THERE IS ADEQUATE PRIMARY TO SECONDARY HEAT TRANSFER IN BOTH SGs, THEN GO TO CP-103. OTHERWISE GO TO LACK OF HEAT TRANSFER, SECTION III B.
S The RCS is saturated. A small break is indicated. Cooldown T with the SGS can be performed while HPI maintains RCS inven-A tory.
T U
S O
O Section III A DATE: 10-1-82 PAGE 20
l BWNP-20007 (6-76)
BABCOCK & WILCOX Nucia NUCLEAR POWER GENERATION DIVISION 74-1126473-00 TECHNICAL DOCUMENT ADEQUATE SUBC00 LING MARGIN HAS BEEN ESTABLISHED 10.0 CONTROL HPI.
10.1 See Specific Rule 2.0.
, 11.0 RESTART RCPs.
11.1 Start two RCPs per OP-302, "RC Pump Ope ra t ion" (see
- Specific Rule 5.0).
11.2 Reopen PZR spray block valve (RCV-13) and establish normal PZR spray flow.
1 11.3 Monitor RCS pressure for 30 minutes to ensure that reopening PZR spray block valve does not cause depressuri-l zation (i.e., failed open PZR spray valve or PZR spray line break).
11.4 F I_F, subcooling margin is lost, THEN close the PZR spr ay block valve (RCV-13) and trip running RCPs.
12.0 IF ANY OF THE OTHER ATOG SYMPTOMS ARE NOT PROPERLY CONTROLLED, THEN go to III B, C or D as appropriate. OTHERWISE CONTINUE.
13.0 PRIMARY TO SECONDARY HEAT TRANSFER IS BEING CONTROLLED P ROPERLY.
FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
S The RCS is subcooled. There may or may not be a bubble in T the pressurizer. SG heat transfer is controlled.
A T
U S
sSection III A l
PAGE DATE: 10-1-82 21
9
\
lil A k
l.0 't TRIP ALL RCPs 70 7 INITI ATE MPI 30 ff ISCLATE POS$1BLE LEAKS if 4.0 EICESSIVE EllstNATE EXCESSa vE HEAT TES _ HEAT TRANSTER.
~
TRANSTER EllSTS IF IT EXISTS NO 90
l l EAINTAIN PROPER SG LEVELS I'
6.0 l $U8C00 LING BARGIN TES EST ABLISHED 1'
T.0 SufERHEATES 1ES C0h0113045 r GO TO SECTION ICC E11ST N0 f
- 3. 0 Cfis EtPTIED TES
& GO TO CP-IO!
NO l
CD 70 CP.103 NEAT TRANSFER IN BOTH SG I
( c0 to ni e s
Is 74-1126473-00 1
s Figure III A LACK OF ADEQUATE SU8C00 LING MARGIN 4
i l
l l
1 i
18.0 C0hfROL NPI i
12.0 THE 11.0 l OthER ATOG GO 10111 B.C OR 0 RE$ FART RCPs & $15P1055 ARE PROPERLY
CONTROLLED PROPERLY.
FURTNER Acil0N AT :
Of SCREfl04 0F GANAGEBENT
i BWNP-20007 (6-76)
BABCOCK & WILCOX OII NuctEAR POWER GENERATION DIYl510N
.; TECHNICAL DOCUMENT 74-1126473-00 7
III B LACK OF HEAT TRANSFER FOLLOWUP ACTION FOR TREATMENT OF LACK OF PRIMARY TO SECONDARY HEAT TRANSFER IN EITHER SG i
1.0 ESTABLISH ADEQUATE SUBC00 LING MARGIN.
1.1 Whenever there is a lack of adequa te subcooling margin, THEN go to Section III A unless the operator has already transferred from that section.
2.0 IF FEEDWATER IS AVAILABLE, THEN GO TO STEP 7.0, OTHERWISE CONTINUE WITH STEP 3.0.
i i
l l
l l
i Section III B l
DATE: PAGE 10-1-82 l
l _ . _ . . . . _ . _.. ___ _ _ _ ~. _ _ . _. _ _-_. .~....__ _...... _ _ - _ .___ _ _ -_- _ ._,, _ _ _ .. - . ,-. ._ _ . . _ . _ . _ _ . . _
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR POWER GENERATION DIVl$10N 74-1126473-00 TECHNICAL DOCUMENT LACK OF FEEDWATER WITH RCS EITHER SUBC00 LED OR SATURATED 3.0 INITIATE EFW.
3.1 Feed both SGs with EFW properly throttled to the appropriate SG 1evel (see Specific Rules 3.0 and 4.0).
3.2 E EFW is not available, THEN use MFW.
3.3 E neither EFW nor MFW is available, THEN attempt to feed at least one SG from an alternate source, e.g., Unit 1 or 2.
3.4 E the EFW system is not operating properly, THEN refe r to the SAD section.
WHEN FW FLOW IS ESTABLISHED, THEN GO TO STEP 7.0. OTHERWISE 4.0, CONTINUE.
5.0 ESTABLISH HPI COOLING.
5.1 Initiate HPI (see Specific Rule 1.0) .
5.2 Open PORV block valve (RCV-ll).
5.3 Open PORV (RCV-10).
5.4 Run one RCP as long as adequate subcooling margin is maintained.
6.0 E NEITHER SG CAN BE FLJ, THEN GO TO CP-104.
S There is no heat transfer to either SG. Natural circula-l T tion does not exist and cannot be induced due to a total l A loss of FW. The SGs are dry and the core must be cooled T by HPI cooling.
U S
O Section III B PAGE DATE: 10-1-82 23
BWNP-20007 (6-76)
BABCOCK & WILCOX Numset s NUCLEAR POwlt GENERAilON OlVisiON 74-1126473-00 TECHNICAL DOCUMENT FEEDWATER HAS BEEN ESTABLISHED BUT THERE IS INADEQUATE HEAT TRANSFER 7.0 ESTABLISH AND MAINTAIN APPROPRIATE SG LEVELS.
7.1 See Specific Rule 4.0.
8.0 g THE CFTs HAVE EMPTIED, THEN GO TD CP-101. OTHERWISE CONTINUE.
]
S The CFIs emptying is an indication of a major LOCA.
T CP-101 provides instructions for long-term cooling A following a major LOCA. Primary to secondary heat T transfer is lost and cannot be regained.
U S
9.0 E AT ANY TIME WHILE ATTEMPTING TO REGAIN HEAT TRANSFER, RC PRESSURE INCREASES TO THE PORV SETPOINT, THEN OPEN THE PORV , REDUCE RCS PRESSURE TO 90 TO 100 PSI ABOVE THE SG PRESSURE AND RESHUT THE PORV.
(
10.0 WHEN ADEQUATE HEAT TRANSFER IS RESTORED, THEN CO TO STEP 17.0.
UNTIL THEN CONTINUE.
1 11.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
j 11.1 Lower SG pressure by adjusting TBVs or ADVs while maintaining level, until secondary T sat is 40 to 60F lower than core exit thermocouple tempe ra ture . Maintain this SG pressure.
12.0 DETERMINE RCP OPERABILITY PER OP-302, "RC Pump Operation". 3 RCPs CANNOT BE BUMPED, THEN GO TO STEP 16.0. OTHERWISE CONTINUE.
Section III B DATE: 10-1-82 PAGE 24
BWNP-20007 (6-76)
BABCOCK & WILCOX Nuuset NUCLEAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74- 126473-00 13.0 USE RCP BUMPS TO INDUCE HEAT TRANSFER.
13.1 Bump an RCP, which is capable of being started, in the loop with the highest level in the SG.
13.2 Allow RCS pressure to stabilize within a 20 psig band befor_e determining if heat trans fer is established .
13.3 WHEN heat transfer is es tablished , THEN go to Step 17.0.
Until then, continue.
13.4 Repeat Steps 13.1 through 13.3 for operable RCPs that have not been bumped. Allow 15 minutes between pump bumps. After all available RCPs hase been bumped, continue.
14.0 FURTHER LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
14.1 Lower SG pressure by adjusting TBVs or ADVs while main-taining the appropriate level , until secondary Tsat is 90 to 110F lower than core exit thermocouple tempera ture .
Maintain this SG pressure.
15.0 START ONE RCP TO INDUCE HEAT TRANSFER.
15.1 F at least one hour has passed since reactor trip AND any RCPs are capable of being started , THEN start and run ene RCP, preferably in a loop with SG 1evel greater tha 30".
16.0 IF, ADEQUATE HEAT TRANSFER HAS NOT BEEN RESTORED , THEN GO TO CP-104.
OTHERWISE CONTINUE.
S There is no heat transfer to either SG. Attempts to T establish heat transfer by natural circulation and A forced flow have failed. The core must be cooled by T HPI.
U G
Section III B DATE: 10-1-82 PAGE 25
BWNP-20007 (6-76) 4 BABCOCK & WILCOX *'
NUCitAR POWER GENERATION DIVI $lON h TECHNICAL DOCUMENT 74-1126473-00 HEAT TRANSFER HAS BEEN RESTORED 17.0 RECOVER FROM HPI COOLING, IF INITIATED.
17.1 Close PORV (RCV-10).
17.2 Close PORV block valve (RCV-ll) if necessary.
17.3 Control HPI (See Specific Rule 2.0).
18.0 CONTROL HEAT TRANSFER RATE.
18.1 Maintain appropriate SG 1evel (see Specific Rule 4.0) and adjust TBVs or ADVs to maintain RC temperature at present i
value.
19.0 F THERE IS ADEQUATE SUBC00 LING MARGIN, THEN START TWO RCPs (IF NONE ARE ALREADY RUNNING) AND CONTINUE WITH STEP 20.0. OTHERWISE GO TO i STEP 21.0.
s 19.1 See Specific Rule 5.0.
I 20.0 PRIMARY TO SECONDARY HEAT TRANSFER IS BEING CONTROLLED PROPERLY.
FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
i S The RCS is subcooled. There may or may not be a bubble T in the pressurizer. SG heat transfer is controlled.
A T
\
s S 21.0 IF_ THERE IS A LACK OF ADEQUATE SUBC00 LING MARGIN, THEN GO TO CP-103.
S The RCS is saturated. A small break is indicated. Cool-T down with the SGs can be performed while HPI maintains A RCS inventory.
T U
S s.
l Section III B l DATE: 10-1-82 PAGE 26 l
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BABCOCK & WILCOX NUCLEAR Powet GENEAATION OlVISION 74-1126473-00 i TECHICAL DOCUMENT J
III C EXCESSIVE HEAT TRANSFER FOLLOWUP ACTIONS FOR TREATMENT OF TOO MUCH PRIMARY TO SECONDARY HEAT TRANSFER
\
1.0 ESTABLISH ADEQUATE SUBC00 LING MARGIN. WHENEVER THERE IS A LACK OF ADEQUATE SUBC00 LING MARGIN, THEN GO TO SECTION III A UNLESS THE OPERATOR HAS ALREADY TRANSFERRED FROM THAT SECTION. OTHERWISE CONTINUE.
2.0 g PRESSURIZER LEVEL FALLS BELOW 50" AND RCS PRESSURE IS DECREASING, THEN INCREASE MAKEUP FLOW.
} 2.1 E PZR level falls below 50" AND RCS pressure is decreas-( ing, THEN start a second makeup pump, take suction from the BWST on low makeup tank level and control flow through the normal makeup injection nozzle with makeup control valve MUV-31.
3.0 g SLBIS HAS ACTUATED ON BOTH SGs, THEN GO TO STEP 23.0. OTHERWISE CONTINUE.
4.0 IF_ SLBIS HAS ACTUATED ON ONLY ONE SG, THEN CLOSE THE EFPT STEAM SUPPLY ISOLATION VALVE ON THE ISOLATED SG (MSV-55 ON SG-A OR MSV-56
> ON SG-B) AND CONTINUE AT STEP 5.0. IF SLBIS HAS NOT ACTUATED, CONTINUE AT STEP 7.0.
5.0 g THE OVERC00 LING HAS BEEN STOPPED, THEN GO TO STEP 16.0.
OTHERWISE CONTINUE.
6.0 MANUALLY ACTUATE SLBIS ON THE UNISOLATED SG AND GO TO STEP 23.0.
O Section III C DATE: PAGE 10-1-82 27
1 i
BWMP-20007 (6-76)
BABCOCK & WILCOX Numsta NUCLEAR POWER GENERATION Olvl510N 74-1126473-00 TECHNICAL DOCUMENT SLBIS HAS NOT ACTUATED 7.0 g EITHER SG LEVEL IS GREATER THAN 90-95% ON THE OPERATE RANGE AND IS INC REASI NG , THEN TRIP THE MFW PUMPS AND CONTINUE. OTHERWISE GO TO STEP 12.0.
7.1 Trip the running MFW pumps.
7.2 Verify auto start of the EFW pumps.
7.3 Ensure proper EFW flow.
8.0 g THE OVERC00 LING HAS BEEN STOPPED, THEN CONTINUE, OTHERWISE GO TO STEP 12.0. i 9.0 CONTROL HEAT TRANSFER TO TWO OPERABLE SGs.
9.1 g MFW has been isolated on a SG, THEN es tabli sh proper l EFW flow to that SG through the EFW bypass valve (FWV-162 on SG-A or FWV-161 on SG-B) while maintaining MFW flow to the other SG (see Specific Rules 3.0 and 4.0).
9.2 Adjust TBVs or ADVs to control steaming on both SGs to maintain RC temperature at its present value.
10.0 E A SG TUBE RUPTURE IS INDICATED, THEN GO TO STEP 25.0. OTHERWISE CONTINUE.
I1.0 FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
S RCS is subcooled with pressure and temperature stable.
T Both SGs are operable steaming either to the condenser A or atmosphere.
T U
S O
Section III C DATE: PAGE 28 10-1-82
BWNP-20007 (6-76)
BABCOCK & WILCOX ER NUCLEAR POWER GENERATION DIVISION 74-1126473-00 TECHNICAL DOCUMENT 12.0 STOP ALL FEEDWATER TO BOTH SGs.
12.1 Completely isolate main and emergency feedwater to both SG.
12.2 Watch SG 1evels; the generator with the fastest level -
decrease is leaking.
13.0 IF THE OVERC00 LING SG, HAS BEEN IDENTIFIED, THEN MANUALLY ACTUATE SLBIS ON THE OVERC00 LING SG AND GO TO STEP 15.0. OTHERWISE CONTINUE.
i 14.0 MANUALLY ACTUATE SLBIS ON BOTH SGs AND GO TO STEP 23.0.
4 4
l l
i Section III C DATE: 10-1-82 PAGE 29
l BWNP-20007 (6-76) l BABCOCK & WILCOX NUCLEAR POWER GENERATION DIYlSION 74-1126473-00 TECHNICAL DOCUMENT l
SLBIS HAS ACTUATED ON ONLY ONE SG 15.0 CLOSE THE EFPT STEAM ISOLATION VALVE ON THE ISOLATED SG (MSV-55 ON SG-A OR MSV-56 ON SGB).
16.0 CONTROL HEAT TRANSFER TO THE UNIS0 LATED SG.
16.1 Do not feed the isolated SG. Allow the isolated SG to boil dry if level is decreasing. After it boils dry, heat t rans fe r on that SG will be lost. DO NOT go to Lack of Heat Transfer Section III B.
16.2 Adjust TBVs or ADV to control stemning on the operable SG to maintain RC temper 7Ature at its present value.
17.0 E A SG TUBE RUPTURE IS INDICATED, THEN GO TO STEP 25.0. OTHERWISE CONTINUE.
18.0 E PRESSURE AND LEVEL ARE STABLE ON THE IS01ATED SG, THEN GO TO STEP 20.0. OTHERWISE CONTINUE.
19.0 FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
S RCS is subcooled with pressure and temperature stable.
T One SG is operable steaming either to the condenser or A atmosphere.
T U
S O
Section III C DATE: 10-1-82 PAGE 30
BWNP-20007 (6-76)
BABCOCK & WILCOX , , , , ,
NUCLEAR POWER GENERATION DIVI $lCN TECHNICAL DOCUMENT 74-1126473-00 20.0 ESTABLISd EFW FLOW TO ISOLATED SG.
20.1 Start the EFW pumps.
20.2 Establish and control EW to the isolated SG while main-
21.0 CONTROL HEAT TRANSFER TO TWO OPERABLE SGs.
21.1 Adjust ADV on the isolated SG to control steaming to the atmosphere. Adjust TBVs or ADV to control steaming on the other SG. Maintain RC temperature at its present value.
1 22.0 FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
1 S RCS is subcooled with pressure and temperature stable.
T Both SGS are operable steaming either to the condenser A or atmosphere.
T U
S i
sSection III C DATE: 10-1-82 PAGE 31
i l
BWNP-20007 (6-76) l BABCOCK & WILCOX Numsen NucteAn POWER GENERADON Dm510N l TECHNICAL. DOCUMENT I
SLBIS HAS ACTUATED ON BOTH SGs 23.0 CLOSE THE EFPT STEAM ISOLATION VALVES ON BOTil SGs (MSV-55 ON SG-A l AND MSV-56 ON SG-B).
l 24.0 RESTORE HEAT TRANSFER TO A SG WITH STABLE PRESSURE AND LEVEL.
24.1 Establish proper EFW flow and SG 1evel in the SG per Specific Rules 3.0 and 4.0.
24.2 g the other SG has been positively identified as the overcooling SG, THEN reopen the MSIVs on this SG. Adjust the TBVs to hcid the RCS temperature constant. Otherwise stean this SG through the ADV and adjust the ADV to hold RCS temperature constant.
t 1
( 25.0 g A SG TUBE RUPTURE IS INDICATED, THEN START A LOCAL SURVEY OF THE MAIN STEAM LINES, AND A SG BORON ANALYSIS, IF NECESSARY TO IDENTIFY THE TUBE-RUPTURED SG, AND GO TO SGTR SECTION III D. OTHERWISE CONTINUE.
26.0 g PRESSURE AND LEVEL ARE STABLE ON THE IS01ATED SG, THEN GO TO STEP 28.0. OTHERWISE CONTINUE.
27.0 FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION MANAGEMENT.
1 1
S RCS is subcooled with pressure and temperature stable.
T One SG is operable steaming to the condenser. One SG A is dry.
T U
S l
O Section III C DATE: 10-1-82 PAGE 32
l BWNP-20007 (6-76)
BABCOCK & WILCOX ,
- nucteam Powes oeNesaicM Ofv4CN 4
74-1126473-00
- TECHICAL DOCUMEllT 28.0 RESTORE HEAT TRANSFER TO THE ISOLATED SG.
I 28.1 Establish proper EFW flow and SG 1evel in the SC per
{ Specific Rules 3.0 and 4.0.
j 28.2 IF the SG in which heat transfer was restored in Step 24.0 has been positively identified as the SG which caused the overcooling (leak downstream of MSIV), THEN reopen the MSIVs on the SG in which EFW flow was restored in Step 28.1. A .* ju s t the TBVs to hold the RCS temperature
! constant. Otherwise stems this SG through the ADV and a
j adjust the ADV to hold RCS temperature constant.
1, 1
29.0 FURTHER ACTION AT THIS POINT WILL BE AT THE DISCRETION OF STATION i MANAGEMENT.
j S RCS is subcooled with pressure and temperature stable.
j T Either one SG is operable steaming to the condenser or l A both SGs are operable with the MSIVs shut and steaming T to atmosphere.
U S
4 1
5 a
i 3
j i
1i Section III C l DATE: 10-1-82 PAGE 33 1
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BWNP-20007 (6-76)
BABCOCK & WILCOX NUM0ft NUCttAt Powie GENetADON OM$CN 74-1126473-00 TECHNICAL DOCUMENT III D SGTR FOLLOWUP ACTIONS FOR SG TUBE RUPTURE 1.0 ESTABLISH ADEQUATE SUBC00 LING MARGIN AND PROPER HEAT TRANSFER.
1.1 E there is adequate subcooling margin and proper primary-t o-secondary heat trans fe r , THEN go to Step 2.0.
Otherwise continue.
1.2 Go to Section III A, III B, and/or III C unless the operator has already transferred from these sections.
2.0 START A LOCAL SURVEY OF THE MAIN STEAM LINES AND A SG BORON ANALYSES TO CONFIRM HIGH RADIATION ALARMS AND TO IDENTIFY THE TUBE RUPTURED SG WHILE CONTINUING WITH STEP 3.0.
3.0 If THE REACTOR HAS TRIPPED, THEN CO TO STEP 6.0.. OTHERWISE CON-TINUE.
4.0 g PRESSURIZER LEVEL IS MAINTAINED, THEN CONTINUE. OTHERWISE TRIP REACT 0't AND GO TO STEP 6.0.
4.1 E PZR level is being maintained by normal makeup, THEN go to Step 5.0. OTHERWISE continue.
4.2 Close letdown isolation valve (MUV-49).
4.3 Manually increase MU as required to maintain PZR level greater than 100". Start a second makeup pump, take suctions from the BWST on low makeup tank level and control flow through the normal makeup injection nozzle with makeup control valve MUV-31. Initiate HPI if neces-sary.
4.4 IF, PZR level cannot be maintained , THEN trip the reactor,
\ and go to Step 6.0. Otherwise continue.
Section III D DATE: 10 1-82 PAGE 34
--,,-,r+--,-,- - . , - , ,e- -
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCttAR POWER GENERATION DIVl$10N 74-1126473-00 TECHNICAL DOCUMENT ,
5.0 SHUTDOWN REACTOR.
5.1 Immediately begin power reduction at greater than 5% per minute per OP-204, " Power Operation".
5.2 IF the reactor trips during runback, THEN continue with Step 6.0 of this section.
5.3 At less than 12% reactor power:
- a. Place the TBVs in manual,
- b. Open the TBVs, then unload and trip the turbine / generator.
- c. Trip the reactor.
- d. Immediately place TBVs back in auto.
5.4 Continue at Step 7.0, 6.0 REACTOR HAS TRIPPED.
6.1 Verify the reactor tripped. Perform the immediate actions and verifications of Section I and II.
6.2 Close letdown isolation valve (MUV-49).
6.3 Manually increase makeup or, if necessary, initiate HPI to maintain PZR level > 100". Throttle HPI once subcooling margin and pzr. level are regained.
6.4 E adequate subcooling margin is lost, THEN trans fe r to Section III A.
6.5 Continue with Step 7.0 7.0 EA LOSS-OF-OFFSITE POWER HAS OCCURRED, THEN GO TO STEP 13.0.
OTHERWISE CONTINUE.
8.0 E OFFSITE POWER IS AVAILABLE, BUT RCPs ARE NOT OPERATING, THEN GO TO STEP 16.0. OTHERWISE CONTINUE.
9.0 E PRESSURIZER LEVEL IS NOT BEING MAINTAINED BY NOIMAL MAKEUP , THEN GO TO STEP 19.0. OTHERWISE CONTINUE.
Section III D PAGE 35 DATE: 10-1-82
BWNP-20007 (6-76)
BABCOCK & WILCOX Numeet NuctEAs POWts GENSATION DIVI $10N 74- 126473-00
'TECHNICR DOCUMENT MODE 1 COOLDOWN 10.0 BEGIN COOLDOWN AND DEPRESSURIZATION.
10.1 Cooldown at up to 100 F/hr by steaming both SG through the TBVs to the condense r . Maintain normal minimum SG 1evels by feeding through the MFW nozzles.
10.2 Depressurize by pressurizer spray as necessary to remain as close as possible to the adequate subcooling margin.
Turn off all pressurizer heaters.
10.3 Bypass the ESAS at < 1700 psig.
10.4 As soon as the tube ruptured SG is identified. THEN switch both the main and emergency feed pump steam supplies to the unaf fected OTSG.
11.0 ISOLATE THE TUBE-RUPTURED SG IF IDENTIFIED s 11.1 AS SOON AS the tube ruptured SG is identified AND the RCS is below 540F, THEN isolate the tube-ruptured SG by closing or verifying closed its respective valves:
Valves SG-A SG-B MFW Block FWV-30 FWV-29 Lo Load Block WV-31 FWB-32 Startup FW Control FWV-40 FVW-39 TBVs MSV-9, -10 MSV-11, -14 EFW Bypass FWV-162 FWV-161 T EFPT Steam Isolation MSV-55 MSV-56 Main Steam MSR Block MSV-30, -32 MSV-29, -31
]j MFPT Steam Isolation MSV-107 MSV-108 >
12.0 CONTINUE COOLDOWN AND DEPRESSURIZATION WITH ONE SG AT UP TD 100 F/hr.
12.1 Co to one (1) RCP in each loop before reach ing 5000F to prevent exceeding core lift limits. Run RCP "B" if
\ pos sib le to provide maximim pres sur izer spray. Ensure the h
SGs are steamed as necessary to prevent the MSSV's from opening.
Section III D DATE: 10-1-82 PAGE 36
- _ _ _ _ )
BWNP-20007 (6-76)
BABCOCK & WILCOX NuusER NUCLEAR POWER GENERAflON DIVl$10N TECHNICAL DOCUMENT 74-1126473-00 12.2 Feed the tube-ruptured SG only as needed to maintain or promote: the low level limit, or tube-to-shell AT require-ments. Steam the tube-ruptured SG only as needed to main-tain: SG 1evel below 90-95% on the operate 'cange, SG pres-sure below the lowest MSSV setpoint (1050 psig) and adequate subcooling margin in the RCS.
12.3 Block steam rupture matrix at steam generator pressure <
725 psig and > 600 spig.
12.4 As RCS pressure and leak rate decrease and RCS inventory and subcooling can be maintained by the makeup system, secure HPI system and establish normal makeup control.
12.5 As cooldown proceeds, sample RCS for boron concentracion.
Borate as necessary to maintain required shutdown margin.
12.6 After going on DHRS cooling, pres sur ize the tube-ruptured SG secondary side with 2-3 psig of N2 ve rpr e s s ur e .
Future action at this point will be at the discretion of station management.
S The RCS is cooling down with one SG isolated with a T tube rupture.
A T
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Section III D DATE: 10-1-82 PAGE 37
BWNP-20007 (6-76)
BASCOCK & WILCOX NUMSN wucteam powen oewmanow omsow 74-1126473-00 TECMICAL DOCUMElli MODE 2 COOLDOWN LOSS OFF OFFSITE POWER HAS OCCURRED 13.0 WHEN OFFSITE POWER IS RESTORED, THEN GO TO STEP 16.0. OTHERWISE CONTINUE.
14.0 BEGIN C00LDOWN AND DEPRESSURIZATION WITH LOSS-OF-OFFSITE POWER.
14.1 Verify that SG 1evels are increasing to the .ippropriate level (See Specific Rule 4.0) with EFW properly throttled (See Specific Rule 3.0).
14.2 AS SOON AS the tube ruptured SG is identified feed it as needed to maintain the low level limit, to promote natural circulation, to maintain adequate subcooling margin, or to maintain tube to shell A T requirements. Steam the tube ruptured SG as necessary to promote natural circulation or maintain level less than 95% on the operate range.
14.3 Start the diesel driven instrument air compressor.
14.4 Depressurize the RCS to as close as possible to the ade-quate subcooling margin curve by opening the PORV. The fuel pin compression limits may be violated.
14.5 As quickly as po s s ible , begin cooldown of the RCS with ADVs using both SGs.
14.6 Initiate a rapid cooldown to 500F (do not exceed a C/D rate of 243F/hr).
14.7 Whenever the RCS becomes 30F colder than the adequate sub-cooling margin curve, THEN depressurize the RCS to as close as possible to the adequate subcooling margin curve by opening the PORV.
Section III D DATE: 10-1-82 PAGE 38 I
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BWWP-20007 (6-76)
BABCOCK & WILCOX Numsta NUCLEAR POWER GENERATION DIVI 510N l 74-1126473-00 1
TECHNICAL DOCUMENT l l 14.8 During the depressurization and cooldown control the ADVs as necessary to prevent the MSSVs from opening.
15.0 GO TO STEP 20.0.
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Section III D 10-1-82 PAGE 39 DATE:
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BWNP-20007 (6-76)
BABCOCK & WILCOX Numett NUCLEAR POWER GENERATION OfVISION TECHNICAL DOCUMENT 74- H26473-00 MODE 2 COOLDOWN REACTOR COOLANT PUMPS NOT RUNNING 16.0 WHEN ADEQUATE SUBC00 LING MARGIN IS OBTAINED, THEN CO TO STEP 18.0.
OTHERWISE CONTINUE.
s 17.0 BEGIN C00LDOWN AND DEPRESSURIZATION WITHOUT RCPs.
17.1 Verify that SG 1evels are increasing to the appropriate SG 1evel (See Specific Rule 4.0) with feedwater properly throttled (See Specific Rule 3.0).
17.2 AS SOON AS the tube ruptured SG is identifed , THEN feed it as needed to maintain the low level limit, to verify natural circulation, to maintain adequate subcooling
\
margin, or to maintain tube to shell A T requirements.
Steau the tube ruptured SG as necessary to promote natural circulation and to maintain the level less than 95% on the operate range.
17.3 As soon as pos s ib le , begin cooldown of the RCS with the TBVs or ADVs initially on both steam generators, if pos s ib ic.
17.4 Initiate a rapid cooldown to 500F (do not exceed a C/D rate of 240 F/hr).
17.5 IF the RCPs cannot be restarted within 10 minutes after they tripped or were tripped, THEN:
U Section III D DATE: 10-1-82 PAGE 40
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLIAE POWER GENERAflON DIVISION 74-1126473-00 TECHNICAL DOCUMENT A. Depressurize the RCS to as close as possible to the adequate subcooling margin curve by opening the PORV.
The fuel pin compression limits may be violated.
B. Continue cooldown of the RCS with the TBVs initially on both steam generators.
C. khenever the RCS becomes 30F colder than the adequate subcooling margin curve, THEN depressurize the RCS to as close as possible to the adequate subcooling margin curve by opening the PORV.
D. Continue cooldown and depressurization in this manner until the RCPs can be restarted per Step 16.0.
17.6 Continue with Step 20.0.
18.0 RESTART RCP'S.
18.1 Start one RCP in each loop. E successful, THEN go to Step 19.0, otherwise continue.
18.2 E unable to start an RCP in each loop, THEN attempt to start both RCPs in either loop. E successful, THEN go to Step 19.0, otherwise continue.
18.3 g only one RCP was started AND the RCP is in loop "B",
THEN go to Step 19.0, otherwise continue.
G
~
O Section III D PAGE 41 DATE: 10-1-82
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4 BWNP-20007 (6-76) i BABCOCK & WILCOX NUM8tt
- NUCLEAR POWta GENERADON DIVI $60N 74-1126473-00 TECHNICAL DOCUMENT l
i
)
19.0 BEGIN COOLDOWN AND DEPRESSURIZATION WITH RCPs.
I 19.1 Ensur e appropriate stema generato r level is maintained (See Specific Rule 4.0). Begin depressurizing the RCS to as close as possible to the adequate subcooling margin ,
I curve by opening the pressurizer spray valve, f
19.2 As quickly as possible, begin cooldown of the RCS with the I TBVs or ADVs initially on BOTH stean generators if pos-sible.
I 19.3 Initiate a rapid cooldown to 500F (do not exceed a C/D
- rate of 240 F/hr).
19.4 Continue spraying the pressurizer as necessary to remain as close as possible to the adequate subcooling margin.
J The fuel pin compression limits may be violated.
19.5 Continue -with Step 20.0, 20.0 IF A SG HAS A STEAM LEAK WHICH CAN NOT BE IS01ATED, THEN GO TO STEP 25.0. OTHERWISE CONTINUE.
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Section III D DATE: 10-1-82 PAGE 42
BWNP-20007 (6-76)
BABCOCK & WILCOX suusER NUCLEAR POWER GENERATION Olvl510N TECHNICAL DOCUMENT 21.0 CONTROL THE TUBE RUPTURED SG TO LIMIT RADIATION RELEASE.
21.1 During the depressurization and cooldown, control the TBVs or ADVs as necessary to prevent the MSSVs from opening.
22.0 ISOIATE THE TUBE RUPTURED SG.
22.1 AS SOON AS the tube ruptured SG is identified AND the RCS is below 540F, THEN isolate the tube ruptured SG by clos-ing or verifying closed its respective valves as follows:
Valves SG-A SG-B MFW Block FWV-30 FWV-29 Lo Load Block FWV-31 FWB-32 Startup FW Control FWV-40 FWV-39 TBVs MSV-9, -10 MSV-11, -14 EFW Bypass FWV-162 FWV-161 EFPT Stean Isolation MSV-55 MSV-56 Main Steam MSR Block MSV-30, -32 MSV-29, -31 MFPT Stean Isolation MSV-107 MSV-108 22.2 Switch emergency feed pump steam supply to the unaffected SG.
22.3 Initiate steaming as necessary to maintain the SG pressure below 1000 psig and SG level below 95% on the operate range on the tube ruptured SG.
O Section III D DATE: 10-1-82 PAGE 43
BWNP-20007 (6-76)
BABCOCK & WILCOX NUCLEAR POwet GENSATION DIVISION 74-1 26473-00 TECHICAL DOCUMEllT 23.0 CONTINUE COOLDOWN WITH APPLICABLE LIMITATIONS.
23.1 When RCS pressure and leak rate decrease and RCS inventory and subcooling can be maintained by the MU system, stop the HPI system and establish normal MU control.
23.2 Continue depressurization and cooldown at the maximum attainable CD rate without exceeding 100F/hr using the SG
. without the tube rupture.
23.3 Decrease the RCS pressure as required to remain as close as possible to the minimum subcooling margin line.
23.4 IF tube to shell AT approaches 150F, slow cooldown as necessary.
24.0 GO TO STEP 30.0.
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BWNP-20007 (6-76)
BABCOCK & WILCOX Numsta NUCLEAR POWER GENERATION DIVISION 74-1126473-00 TECHNICAL DOCUMENT MODE 3 COOLDOWN 25.0 IF THE SG WITH THE STEAM LEAK ALSO HAS THE TUBE RUPTURE, THEN GO TO STEP 27.0, OTHERWISE CONTINUE.
26.0 PREPARE SECONDARY PLANT FOR C00LDOWN USING SG WITH TUBE RUPTURE.
26.1 Open the MSIV on SG WITH tube rupture.
26.2 Feed the SG without the . tube rupture as necessary (N 100 gpm) to maintain tube to shell AT requirements and/or promote natural circulation.
26.3 Use SG with tube rupture to cooldown.
26.4 Go to Step 28.0.
27.0 PREPARE SECONDARY PLANT FOR COOLDOWN USING SG WITHOUT TUBE RUPTURE.
27.1 Open the MSIV on SG WITHOUT tube rupture.
27.2 Feed the SG with the tube rupture as necessary (N 100 gpm) to maintain tube to shell AT requirements and/or promote natural circulation.
27.3 Use the SG without tube rupture to cooldown.
28.0 SWITCH THE EFPT STEAM SUPPLY TO THE OPERABLE SG.
29.0 CONTINUE COOLDOWN WITH APPLICABLE LIMITATIONS.
29.1 When RCS pressure and leak rate decrease and RCS inventory and subcooling can be maintained by the MU system, stop the HPI system and establish normal MU control. Continue depressurization and cooldown at the maximum attainable CD rate without exceeding 100F/hr using the operable SG.
29.2 Decrease the RCS pressure as required to remain as close as possible to the minimum subcooling margin line.
29.3 Feed the SG with the steam leak as necessary (N100 gpm) to maintain tube to shell AT requirements and/or promote j natural circulation.
Section III D DATE: 10-1-82 PAGE 45
I BWNP-20007 (6-76)
BABCOCK & WILCOX Numste i
NUCitAR POWER GENERATION Divl580N 74- 126473-00 s TECHICAL DOCUMENT 29.4 E tube to shell A T approaches 150F, slow cooldown as necessary.
29.5 g tube to shell AT exceed s 150F, THEN stop cooldown.
Resume cooldown when tube to shell AT is less than 150F.
30.0 CONTINUE C00LDOWN USING ONLY ONE SG. GO TO CP-102. OBSERVE THE FOLLOWING ADDITIONAL PRECAUTIONS:
30.1 When stemning is no longer possible drain the SG as necessary to the condenser to prevent filling the SG.
30.2 After going to DHRS cooling, pressurize the tube-ruptured SG secondary side (if possible) with 2-3 psi of N2 ove r-i pressure.
. 30.3 Continue cooldown and drain the primary side of the SGs as soon as possible to stop the leak.
, S The RCS is cooled to below 500F and cooldown T continues with one SG. One SG has a tube rupture.
, A The RCS may be, with or without RCPs running or T offsite power. One of the SGs may not be operable U due to an unisolatable steam leak.
S I
i Section III D DATE: 10-1-82 PAGE
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BWNP-20007 (6-76) :
BABCOCK & WILCOX NucttAR POWER GENERATON DIVISCN 74-1126473-00
/' TECHICAL DOCUMEllT CP-101 A LARGE LOCA HAS OCCURRED AND THE CORE FLOOD TANKS ARE EMPTYING 1.0 VERIFY AUTOMATIC ACTIONS.
1.1 Check ESAS actuation per Section II, Step 8.0.
1.2 When BWST level reaches 10 ft, level, THEN begin makeup to BWST with borated water.
2.0 NOTIFY PERSONNEL.
2.1 Notify Duty Emergency Coordinator.
i 3.0 E THE RCS REPRESSURIZES ABOVE THE LPI DISCHARGE PRESSURE, THEN:
A. E there is heat transfer to SG s THEN go to CP-103.
B. IF there is NO heat transfer to SGs THEN go to CP-104.
4.0 CONTROL HPI, LPI AND RB SPRAY.
4.1 See Specific Rule 1.0.
4.2 WHEN the BWST low level alarms, THEN align HPI to take suction from the LPI system.
I A. Open DHV-Il and DHV-12, LPI discharge to MU Pump suction.
B. Close MUV-58 and MUV-73, BWST to HPI pumps.
4.3 Isolate DH rooms.
l A. Close DH room floor drain valves.
, B. Close DH room purge damper valves.
C Close water tight doors.
k Section CP-101 DATE: 10-1-82 PAGE g
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BWNP-20007 (6-76)
- BABCOCK & WILCOX . . ,
NUCitAR POWtA GENERATION DIVI $lON 74-1i26473-00 TECHNICAL DOCUMENT 4.4 WHEN the BWST low low level alarms, THEN align LPI system to take suction from the reactor building sump.
A. Verify RB sump pumps in " Pull-to-Lock" and WDV-3 and
-4 closed.
B. Open RB sump outlet valves (DHV-42 and -43).
C. Open RC isolation to DHRS (DHV-3 and -4).
D. Isolate LPI suc tion from the BWST by closing BWST I
outlet valves (DHV-34 and -35).
E. Close NaOH tank discharge valves (BSV-35 and -37).
4.5 Throttle LPI and RB spray flows to prevent pump runout.
5.0 WHEN LPI FLOW HAS BEEN IN EXCESS OF 1000 gpm in each injection line for at least 20 minutes, THEN:
A. Stop HPI pumps.
B. Close HPI valves (MUV-23, -24, -25, and -26).
C. Isolate the CFT outlet valves.
6.0 ISOIATE MAJOR LINE CONTAINMENT PENETRATIONS.
6.1 IF core cooling is being maintained by the HPI/LPI/CFT systans, THEN stop the EFW pumps AND close the following I
valves to isolate the SGs.
Valves SG-A SG-B MFW Block FWV-30 FWV-29 Lo Load Block WV-31 FWB-32 Startup FW Control FWV-40 FVW-39 TBVs MSV-9, -10 MSV-11, -14 EFW Bypass FWV-162 FWV-161 EFPT Stean Isolation MSV-55 MSV-56 Main Steam MSR Block MSV-30, -32 MSV-29, -31 MFPT Steam Isolation MSV-107 MSV-108 l Section CP-101 DATE: 10-1-82 PAGE 48 l
BWNP-20007 (6-76)
BABCOCK & WILCOX ER NUCLEAR POWER GENERATION DIVI $10N
. 74-1126473-00 TECHNICAL DOCUMENT 6.2 WHEN:
- a. RB pressure increases above 4 psig, E
- b. RCS pressure decreases below 1500 psig, 0,R
- c. RB radiation increases above the high radiation limit, THEN ensure that the RB isolation valves are closed pe r "RB Isolation System" SAD, EDS-112-11-112.
6.3 E the RB isolation system is not operating properly, THEN refer to the SAD section.
7.0 ESTABLISH LONG TERM COOLING.
7.1 Shutdown turbine, FW, and steam systems when time permits.
7.2 Close PORV block valve (RCV-110).
7.3 Begin secondary plant shutdown pe r OP-209, " Plant Cool-down".
7.4 Continue LPI cooling per OP-404, "DHRS", until further instructions are given by management.
7.5 g any of the following occur:
- b. RB temperature is greater than or equal to 130F, E
- c. RB radiation is greater than the high radiation limit, d.
RB H2 concentration is greater than or equal to 3.5 O
volume percent, THEN start three RB coolers with maximum cooling water flow.
7.6 Monito r gas and particulate activity and rad ia t ion levels to determine if penetration areas and emergency pump rooms are safe for personnel entry.
Section CP-101 DATE: 10-1-82 PAGE 49
BWNP-20007 (6-76)
BABCOCK & WILCOX III NUctEAR POWER GENERAftoN DIYlSION 74-ti26u3-00 g T ECHNICAL DOCUMENT ,
, 7.7 Sample the RCS fluid for boron concentration to ensure that the RCS is not being diluted. E the RCS is being diluted , THEN check for leaks into the RB ( i . e . , RB cooler ,
cooling water, main or emergency FW, NSCCW).
7.8 Periodically sample RCS fluid for pH, boron and isotopic concentration once stable temperature are reached.
7.9 Monitor RB fo r H2 . Initiate hydrogen purge before H2 con-a centration reaches 3.5%. E RB radiation exceed s the high limit, DIEN stop the H2 purge.
i
.l CAUTION g NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY ESAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF RADIO-ACTIVE GAS OR LIQUID.
8.0 ESTABLISH DILUTION FLOW TO THE RV.
8.1 As soon as practicable within twenty-four hours, estab-I lished dilution flow to the RV to prevent boron precipita-tion.
Section CP-101 DATE: 10-1-82 PAGE 50
BWNP-20007 (6-76)
BABCOCK & WILCOX NumER HUctEAR POWER GENERATION OlviSION _ _
TECHNICAL DOCUMENT CP-102 NORMAL COOLDOWN 1.0 START RCPs.
1.1 g any RCps are running, THEN go to Step 2.0, otherwise continue.
1.2 g natural circulation is in progress, THEN start RCP's per OP-302 RCP operation. One operat ing RCP per loop is de s ired . See Specific Rule 5.0.
2.0 g PZR SPRAY IS UNAVAILABLE, THEN USE THE PORV TO DEPRESSURIZE THE RCS.
3.0 E WO SGs ARE IN SERVICE, THEN GO TO STEP 5.0. OTHERWISE CONTINUE.
4.0 PREPARE FOR COOLDOWN WITH A DRY SG.
4.1 Calculate the existing tube-to-shell A T for the dry SG.
I SG Shell T/C AT= - Teold 5
= F. This value must not exceed 100F.
4.2 WHEN the A T as de termined in Step 4.1 above is < 100F, open the TBVs or ADVS on the operable SG and commence cooldown. M NOT exceed 100F tube-to-shell A T on the dry SG.
O Section CP-102 DATE: AGE 10-1-82 51
BWNP-20007 (6-76)
BABCOCK & WILCOX ,,,,
NUCLEAR POWER GENtEATON DIYlSON 74-1126473-00 TECHNICAL DOCUMENT
, 5.0 CONTROL HPI.
i 5.1 See Specific Rule 1.0.
5.2 IF the BWST low level alarms, THEN align HPI to take suction from the LPI system.
A. Open DHV-11 and DHV-12, LPI discharge to MU pump
- suction.
B. Close MUV-58 and MUV-73, BWST to HPI pumps.
! 5.3 IF the BWST low low level alarms , THEN align LPI to take suction from the reactor building sump.
A. Verify RB sump pumps in " pull-to-lock" and WDV-3 and 4 closed.
B. Open RB sump outlet valves (DHV-42 and -43).
C. Open RC isolation to DHRS (DHV-3 and -4).
D. Isolate LPI suction from the BWST by closing BWST outlet valves (DHV-34 and -35).
E. Close NaOH tank discharge valves (BSV-35 and -37).
i 6.0 CONTINUE C00LDOWN. ,
j 6.1 Continue plant cooldown per OP-209 with HPI pump suction provided by LPI discharge from the sump.
6.2 Place RCS on the DHR system as soon as conditions for DHR operation are met.
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1 Section CP-102 DATE: 10-1-82 PAGE 52 l
BWNP-20007 (6-76)
BABCOCK & WILCOX NUMBER NUCLEAR POwlt GENERATION DIVI 510N 74-1126473-00 TECHNICAL DOCUMENT CP-103 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT LEAVES THE RCS SATURATED WITH SG(s) REMOVING HEAT 1.0 VERIFY THAT HEAT TRANSFER IS BEING CONTROLLED.
1.1 Verify maximum HPI flow (see Specific Rule 1.0).
1.2 Verify SG levels are at 95% on the operate range.
2.0 IF_ THE C_0RE FLOOD TANKS ARE EMPTYING, (DUE TO A LARGE BREAK LOCA),
THEN GO TO CP-101, 3.0 ENSURE THE CFT ISOIATION VALVES (CFV-5 and -6) REMAIN OPEN.
4.0 BEGIN C00LDOWN OF RCS.
4.1 Increase SG steaning by opening the TBVs or ADVs.
4.2 Verify that SG(s) continue to provide a heat sink for the RCs by;
- a. remaining pressurized AND b, core exit T/Cs decrease as SG pressure is lowered.
4.3 Continue saturated cooldown by decreasing SG pressure.
4.4 E the RCS does not cooldown as the SGs are depressurized, bump an RCP to reestablish heat transfer via natural circulation.
4.5 g cooling down with a dry SG, THEN ensure that the tube-to-shell AT on the dry SG does not exceed 100F. The dry SG may be trickle fed about 100 gpm to cool the secon-dary side.
5.0 IF HEAT TRANSFER IS LOST IN BOTH SG, THEN CONTINUE , OTHERWISE GO TO EP 13.0.
Section CP-103 DATE: PAGE 53 10-1-82
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BWNP-20007 (6-76) '
. BABCOCK & WILCOX Numeen
, NucteAn Powee oeNenADoM Dm560N 74-1126473-00 TECHNICAL DOCUMENT
- l 1
6.0 INITIATE HPI COOLING.
6.1 Initiate HPI (See Specific Rule 1.0) .
6.2 Open PORV Block Valve (RCV-11). !
6.3 Open PORV (RCV-10),
f
, 6.4 Run one RCP as long as adequa te subcooling margin is maintained.
1
?
7.0 IF AT ANY TIME WHILE PERFORMING STEPS 8.0 THROUGH 11.0, ADEQUATE
, PRIMARY TO SECONDARY HEAT TRANSFER IS RESTORED, THEN CO TO STEP 13.0.
1 8.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER, 1
1 8.1 Lower SG pressure by adjusting TBVs or ADVs while main-taining . level, until secondary Tsat is 40 to 60F lower than core exit T/C temperature. Maintain this SG pressure.
9.0 DETERMINE RCP OPERABILITY PER OP-302, "RC PUMP OPERATION" . IF RCPs CANNOT BE BUMPED, THEN CONTINUE C00LDOWN WITH CP-104. OTHERWISE CONTINUE.
! BUMP RCPs TO INDUCE HEAT TRANSFER.
9.1 Bump a RCP , which is capable of being started, in the loop with the highest SG 1evel.
l 9.2 Allow RCS pressure to stabilize within a t20 psig band before determining if heat trans fer has been established .
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g Section CP-103 DATE: PAGE 10-1-82 54
BWNP-20007 (6-76)
BABCOCK & WILCOX NUaA8ER NUCLEAR POWER GENERAflON DIVI $10N TECHNICAL DOCUMENT 74-1126473-00 9.3 E heat transfer has nu been res to red , THEN repeat Steps 9.1 and 9.2 for operable RCPs that have not been bumped.
Allow 15 minutes betwen bumps.
9.4 E all operable RCPs have been bumped and heat trans fer has NOT been restored, THEN continue with Step 10.0.
10.0 FURTHER LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
10.1 Lower SG pressure by adjusting TBVs or ADVs while main-taining the appropriate level, unt il secondary Taat is 90 to 110F lower than core exit T/C t empe ra t ure . Maintain this SG pressure, 11.0 START ONE RCP TO INDUCE HEAT TRANSFER, 11.1 E at least one hour has passed since reactor trip and any RCP s are capable of being started, THEN start and run one RCP, preferably in a loop with SG 1evel greater than 30".
12.0 E PRIMARY TO SECONDARY HEAT TRANSFER HAS NOT BEEN ESTABLISHED, THEN GO TO CP-104 OTHERWISE CONTINUE C00LDOWN AT STEP 13.0.
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Section CP-103 DATE: 10-1-82 PAGE 55
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BABCOCK & WILCOX "0EI NUCLEAR POWER GENERATION DIV1510N 74-1126473-00 TECHNICAL DOCutlENT l
13.0 WHEN THE RCS BECOMES ADEQUATELY SUBC00 LED, THEN START 'IWO RCPs.
13.1 Determine if subcooled conditions exist by checking exit T/Cs AND hot leg RTDs. With proper HPI flow subcooling margin will be restored.
13.2 WHEN the RCS becomes subcooled, THEN start two RCPs in 4 accordance with OP-302, "RCP O pe ra t ion" . (see Specific t
\ Rule 5.0).
14.6 E THE RCS REMAINS ADEQUATELY SUBC00 LED AFTER STARTING THE RCPs, THEN GO TO CP-105. OTHERWISE IMMEDIATELY TRIP RUNNING RCPs. IF PRIMARY-TO-SECONDARY HEAT TRANSFER IS LOST, GO BACK TO STEP 5.0.
OTHERWISE CONTINUE.
15.0 IF, THE RCS BECOMES ADEQUATELY SUBC00 LED WITH ADEQUATE PRIMARY-TO-
[
kg SECONDARY HEAT TRANSFER ANY TIME DURING THE COOLDOWN, THEN, GO TO CP-105.
16.0 E AT ANY TIME THE RCS BECOMES SUPERHEATED AS INDICATED BY CORE EXIT EXIT T/Cs (SEE FIGURE 3), THEN GO TO SECTION ICC.
17.0 E BEFORE REACHING A BWST LO-LO-LEVEL (3 FEET 9 INCHES), LPI FLOW HAS BEEN IN EXCESS OF 1000 GPM IN EACH INJECTION LINE FOR AT LEAST 20 MINUTES, THEN STOP HPI PUMPS AND RCPs, CLOSE THE CFT ISOLATION i VALVES AND GO TO STEP 1" } ,0THERWISE CONTINUE.
17.1 Stop HPI r:W%s tcept for normal makeup pump.
17.2 Close '+ J (MUV-23, -24, -25 and -26).
17.3 Close LM-to-Hei (valves (DHV-11 and -12).
17.4 Open RC isolation to DDRS (DHV-3 and -4).
17.5 Isolate HPI system suction from the BWST by closing BWST outlet valves (MUV-58 and -73).
17.6 Trip RCPs, if running, and establish normal makeup to maintain seal injection flow to all RCPs in anticipation
'- of immediate restart should LPI flow be interrupted.
Section CP-103 DATE: 10-1-82 PAGE 56
BWNP-20007 (6-76)
BABCOCK & WILCOX Nuxsta NUCttAt POWER GENERAllON DIVISION 74-1126473-00 TECHNICAL DOCUMENT 17.7 If necessary, throttle the LPI valves (DHV-Il0 and -111) to balance flow between trains and to maintain flow per pump as indicated on FIS-43 and -44 below the runout limit.
17.8 Close the CFT isolation valves.
17.9 Go to Sten 19.0.
18.0 WHEN THE BWST LO-LO LEVEL (3 FEET 9 INCHES) IS REACHED, THEN ALIGN THE HPI SYSTEM TO TAKE SUCTION FROM THE RB SUMP USING THE LPI SYSTEM TO PROVIDE HPI PUMP SUCTION, 18.1 Ve rify RB sump pumps in " Pull-To-Lock" and WDV-3 and -4 closed.
18.2 Open RB sump outlet valves (DHV-42 and -43).
18.3 Open LPI-To-HPI valves (DHV-11 and -12).
18.4 Isolate HPI system suction from the BWST by closing BWST outlet valves (MUV-58 and -73).
19.0 WHEN THE BWST LO-LO LEVEL (3 FEET 9 INCHES) IS REACL'ED , THEN TRANSFER LPI AND RB SPRAY SUCTION TO RB SUMP.
19.1 Ensure the RB sump outlet valves (DHV-42 and -43 are open).
19.2 Isolate LPI system suction from the BWST by clos ing BWST outlet valves (SHV-34 and -35).
20.0 IF IN HPI/LPI " PIGGYBACK" MODE, THEN CONTINUE. OTHERWISE GO TO STEP 22.0.
21.0 TERMINATE HPI/LPI PIGGYBACK OPERATION.
21.1 WHEN HPI/LPI " piggyback" operation has been supplying at least 1000 gpm to each loop for 20 minutes AND during this 20 minutes the RCS pressure has been less than the maximum pressure for LPI operation alone, THEN:
Section CP-103 DATE: 10-1-82 PAGE 57 '
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BABCOCK & WILCOX NUMBER NuctEAR POWER GENERAfiON DIVISION 74-1126473-00 TECHNICAL DOCUMENT
- a. Open the LPI-to-RCS valves (DHV-5 and -6),
- b. Stop the running HPI pumps except fo r normal makeup pump.
- c. Close LPI-to-HPI valves (DHV-ll and -12).
- d. Trip RCPs, if running, and establish normal makeup to maintain seal injection flow to all RCPs in anticipa-k tion of immediate restart should LPI flow be inter-ru p t ed .
- e. Close the CFT isolation valves.
22.0 CONTINUE C00LDOWN IN LPI/DHRS OR SG-ONLY C00LDOWN MODE.
4 21.1 IF there is an unisolable LOCA, THEN go to Step 24.0.
OTHERWISE continue at Step 22.2.
21.2 Prior to the RCS being cooled to 280F and 300 psig, sample the pr aary coolant for isotopic analysis and notify the plant superintendent of results before placing LPI/DHRS in
. s e rvic e.
22.3 IF the decision has been made to complete cooldown with LPI/DHRS, THEN continue with Step 24.0 OTHERWISE cooldown solely with SG(s) in accordance with OP-209, " Plant Cooldown".
4 w CAUTION DO NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY ESAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF RADIO-ACTIVE CAS OR LIQUID.
Section CP-103 DATE: 10-1-82 PAGE 58
BWNP-20007 (6-76)
BABCOCK & WILCOX uumste NucitAR POWER GENERADON OlVISION 74-1126473-00 TECHNICAL DOCUMENT 23.0 WHEN THE RCS DEPRESSURIZES TO LESS THAN 150 PSIG, THEN CLOSE OR VERIFY CLOSED ALL HIGH POINT VENT VALVES.
1 24.0 CONTINUE C00LDOWN ON LPI SYSTEM.
24.1 _IF, only one LPI train is operable OR the RCS is not sub-cooled, THEN go to Step 24.3. OTHERWISE continue at Step '
24.2.
24.2 WHEN RC pressure / temperature is below 300 psig and 280F (the maximum limit of the DHRS), THEN establish core cooling with LPI loop A in DH mode per OP-404, "DHRS".
Ensure that the DH pump does not lose suction, i.e., the water level is maintained above the DH drop line off the hot leg.
24.3 Monitor core A T by comparing incore T/Cs and DH cooler outlet temperature.
24.4 Continue RCS cooldown to 140F with core cooling provided by DHRS and RCS pressure controlled by LPI or PZR.
24.5 g core cooling is provided by DHRS AND RCS pressure is below 125 psig, THEN place SGs in wet layup AND close or verify closed the PORV (RCV-10).
25.0 ESTABLISH LONG TERM COOLING PER CP-101 STEPS 7.0 - 8.0.
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Section CP-103 DATE: PAGE 10-1-82 59
1 BWNP-20007 (6-76)
BABCOCK & WILCox " " "
NUCLEAR POwlt GENERAtlON DIVISION I i
TECHNICAL DOCUMENT 74-1126473-00 i
i CP-104 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT LEAVES THE PLANT IN HPI COOLING 1.0 OPEN OR VERIFY OPEN PORV (RCV-10) AND PORV BLOCK VALVE (RCV-ll).
., 2.0 g THE RCS IS SATURATED, THEN ENSURE MAXIMUM HPI FLOW PER FIGURE 1.
l 2.1 See Specific Rule 1.0.
l 3.0 WHEN THE RCS BECOMES SUBC00 LED, THEN START A RCP PER SPECIFIC RULE 5.0 AND CONTROL HPI PER SPECIFIC RULE 2.0, 4.0 g AT ANY TIME DURING HPI COOLING PRIOR TO DHRS COOLING:
i A. THE CORE EXIT T/Cs INDICATE THAT A SATURATED RCS BECOMES SUBC00 LED WITH FW AND SGs STILL AVAILABLE, BUT PRIMARY TO SECONDARY HEAT TRANSFER DOES NOT EXIST, 0,,R_
E C. AN RCP BECOMES AVAILABLE FOR BUMPING AND FW IS AVAILABLE.
THEN GO TO STEP 8.0 0F CP-103 TO RESTORE PRIMARY-TO-SECONDARY O
HEAT TRANSFER.
5.0 g PRIMARY-TO-SECONDARY HEAT TRANSFER IS RESTORED AND THERE IS
- ADEQUATE SUBC00 LING MARGIN AT ANY TIME PRIOR TO DHRS COOLING, THEN GO TO CP-105.
Section CP-104 DATE: 10-1-82 PAGE 60
BWNP-20007 (6-76)
BABCOCK & WILCOX Num En NuctEAn ROWER GENERATION DIVl3;ON TECHNICAL DOCUMENT 6.0 IF PRIMARY-TO-SECONDARY HEAT TRANSFER IS RESTORED WITHOUT ADEQUATE SUBC00 LING MARGIN AT ANY TIME PRIOR TO DHRS COOLING, THEN GO TO CP-103.
7.0 WHEN THE RCS IS AT 280F AND 300 PSIG, THEN GO 10 OP-404, "DHRS" TO ESTABLISH DHRS COOLING.
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I BWNP-20007 (6-76)
BABCOCK & WILCOX NMet wucteam rowse oeweeAriou oivision
( TECHNICAL DOCUMENT 74-1126473-00 CP-105 TRANSIENT TERMINATION WITH SG(s) REMOVING HEAT AND WITH A SUBC00 LED RC FOLLOWING AN OCCURRENCE THAT MAY REQUIRE PRESSURIZER RECOVERY OR SOLID PLANT COOLDOWN
( 1.0 CLOSE OR VERIFY CLOSED ALL HIGH POINT VENTS. l 2.0 E THERE IS A BUBBLE IN THE PRESSURIZER, THEN GO TO CP-102.
OTilERWISE CONTINUE.
3.0 VERIFY PORV (RCV-10) AND PORV BLOCK VALVE (RCV-ll) ARE CLOSED.
4.0 CONTROL HPI FLOW.
4.1 See Specific Rule 2.0.
4.2 Establish letdown flow.
4.3 Control HPI and le td avn flow to maintain 30F margin relative to the adequate subcooling margin curve of Figure
- 2. If necessary, maintain maximum HPI flow per Figure 1.
5.0 E THE DECISION IS MADE NOT TO TRY TO ESTABLISH A BUBBLE IN THE PZR, THEN GO TO STEP 8.0 AND PROCEED WITH A SOLID PLANT C00LDOWN.
6.0 ESTABLISH A BUBBLE IN THE PRESSURIZER.
6.1 Turn on all available PZR heaters.
6.2 Monitor the increase in PZR water temperature until PZR tempe rature reaches satur ation for the existing RC l
pressure. At this point, a bubble will be formed.
6.3 WHEN a bubble is established in the PZR, THEN lower PZR level to approximately 200 inches. E a bubble cannot be formed , THEN go to Step 8.0 and proceed with a solid plant cooldown.
7.0 GO TO CP-102.
Section CP-105 DATE: 10-1-82 PAGE g
BWNP-20007 (6-76)
BABCOCK & WILCOX NumstR NUCLEAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74-1126473-00 8.0 BEGIN SOLID PLANT COOLDOWN.
8.1 Close letdown isolation valve (MUV-49).
8.2 Using small incremental steps, open and control TBVs or ADVs so as to maintain a cooldown rate less than 100F/hr while maintaining adequate subcooling margin.
8.3 Control HPI flow to reestablish 30F margin relative to the adequate subcooling margin curve of Figure 2 prior to each incremental temperature / pressure change.
8.4 IF cooling down with a dry SG, THEN ensure that the tube-to-shell A T on the dry SG does not exceed 100F.
8.5 Continue cooldown while attending to the overall plant per CP-102.
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Section CP-105 PAGE 63 DATE: 10-1-82
BWNP-20007 (6-76)
BABCOCK & WILCOX Numna i
/ NUCLEAR POWtt GENtaATION DIVI 510N
[ 74-1126473-00 TECHNICAL DOCUMENT V
i SPECIFIC RULE AND/OR GUIDELINE 1 - INITIATION OF MU/HPI A. HPI SUBCOOLING RULE 1.0 E the RCS subcooling margin is lost THEN, two HPI pumps should be run at full capacity.
1.1 Initiate HPI by starting two HPI pumps with suction from
.. the BWST and flow through the HPI injection lines, (i.e.,
do not manually actuate ESAS).
2.0 E the ESAS is actuated and the HPI is automatically started, THEN, two HPI pumps should be run at full capacity.
2.1 Verify two HPI pumps have started upon ESAS actuation and suction has switched to the BWST.
O 3.0 E HPI is actuated by Step 1.0 or 2.0 above, THEN, 3.1 Verify indicated HPI flow is equal to or greater than the
" minimum allowed" HPI flow curve of Figure 1.
3.2 E one HPI pump fails to start, THEN perform the following actions:
- a. Verify the makeup pump which failed to start is lined up to received power from the start-up trans former on
- the operating diesel generator (s).
- b. Establish pump suction from the BWST.
- c. Verify the makeup t a nk ' outlet valve is closed
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- d. E a diesel generator has failed to statt, THEN adjust loads as necessary on the operating diesel generator to supply power to the makeup pump.
- e. Place the makeup pump in service.
3.3 E HPI flow cannot be increased to at least the " minimum allowed" value of Figure 1, THEN maintain the maximum
) attainable HPI flow wh ile investigating the HPI system i problem. Refer to the SAD Section, "RCS Pressure and Inventory Control."
Specific Rules DATE: 10-1-82 PAGE 64
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BWNP-20007 (6-76) l BABCOCK & WILCOX BER NUCLEAR POWER GENERATION DIVISION ;
TECHNICAL DOCUMENT 74-1126473-00 1
3.4 Balance HPI flow as indicated on the ESAS panels.
- a. Balance inj ection flows by adjusting MUV-23 and MUV-24 in Loop A and MUV-25 and MUV-26 in Loop B as neces-s ary .
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i Specific Rules DATE: 10-1-82 PAGE 65
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BABCOCK & WILCOX Numete NUcLIAR POWER GENEGATON DIVI $lON 74-1126473-00 J l TECHNICAL DOCUMENT SPECIFIC RULE AND/OR CUIDELINE 2 - HPI FLOW CONTROL A. GUIDELINES FOR HPI TERMINATION OR THROTTLING 1.0 HPI operation may be terminated if the LPI system has been started and has been flowing at a rate in excess of 1000 gpm in each injection line for 20 minutes.
2.0 HPI may be throttled any time the reactor coolant subcooling margin is restored.
HPI may be stopped any time the reac tor coolant subcooling margin is restored and pressurizer level is on scale " low" Q 50") and increasing. Normal makeup should be restarted. The one exception to this guideline is the case where core cooling is provided solely by HPI. In this case HPI can be throttled s when the subcooling margin is restored but should not be stopped until secondary heat removal is established, even though the pressurizer will be solid.
2.1 WHEN RCS subcooling is equal to or greater than the adequate subcooling margin curve of Figure 2 as determined f by both incore T/Cs and RTDs, THEN control HPI pe r the l following.
l a. IF any RCP s are operating, THEN detennine the RC temperature with the cold leg RTDs and reduce HPI flow l
to maintain the RC P/T within Regions I and II of Figure 2.
- b. IF NO RCPs are operating, THEN determine the RC tem-perature by averaging the five highest incore ther-
- mocouple temperature readings and reduce HPI flow to maintain the RC P/T within Region II only.
1 a
I Specific Rules DATE: 10-1-82 PAGE g
BWNP-20007 (6-76)
BABCOCK & WILCOX - NuusEn NUCLEAR POWER GENERATION DIVI 510N 74-1126473-00 TECHNICAL DOCUMENT 3.0 The HPI mus t be throttled to prevent pump runout and cavitation damage. The maximum allowable flow per pump is 545 gpm.
4.0 The HPI low flow limit is 90' gpm. Total pump flow should not be throttled below this limit.
5.0 HPI must be throttled to limit subcooling and thereby prevent exceeding the brittle fracture limits of the reactor vessel dien there is no forced RCS flow.
6.0 IF HPI is throttled, THEN, adjust flow with HPI valves MUV-23 and MUV-24 in loop A and MUV-25 and MUV-26 in loop B, as necessary.
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Specific Rules DATE: 10-1-82 PAGE g
BWNP-20007 (6-76)
BABCOCK & WILCOX . , ,
NUCLEAR POWER GENERATION DIVl510N 74- 126473-00 TECHNICAL DOCHIENT SPECIFIC RULE AND/OR GUIDELINE 3 - EFW THROTTLING j
l A. RULES FOR EFW THROTTLING 1
1.0 EFW must be turned on full if natural circulation stops and the l 1
4
~
steam generator level is below the setpoint. It can be throttled when natural circulation starts.
2.0. EFW must be turned on full if its actuation was delayed. It can be throttled when natural circulation starts.
3.0 EFW must be turned on full if it is injecting into only one ge ne ra to r. It can be throttled when natural circulation starts.
4.0 EFW flow into the steam generators should be continuous at all times until the setpoint is reached.
4 S tean generator level must be continually raised to the applicable setpoint; the steam generator level must never be allowed to decrease if level is still below the applicable setpoint unless excessive primary to secondary heat trans fer exists.
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Specific Rules DATE: 10-1-82 PAGE 68
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BWNP-20007 (6-76) !
l BABCOCK & WILCOX NUMBER NUCLEAR POWER GENERATION DIVISION TECHNICAL DOCUMENT 74-1126473-00 B. GUDELINES FOR EFW THROTTLING 1.0 EFW may be throttled any time it is started after loss of main FW, if it is injecting into both steam generators.
2.0 EFW may be throttled any time after it is started and natural circulation exists in one or both steam generators.
3.0 g RC tenperature is to be stabilized, THEN throttle EFW to maintain SG pressure less than 100 psig below the turbine h eader pres sure se tpo int (e.g., throttle EFW to maintain SG pressure above 910 psig after a reactor trip when the turbine header setpoint has been biased to 1010 psig).
4.0 ga cooldown is required, THEN throttle EFW as necessary to limit the cooldown rate to the max icauia allowed rate (normally 100 F/hr).
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Specific Rules DATE: PAGE 10-1-82
BWNP-20007 (6-76)
'~
BABCOCK & WILCOX NUCLEAR POWER GENERATION DIVtslON (J '
TECHNICAL DOCUMENT 74-1126473-00 SPECIFIC RULE AND/OR GUIDELINE 4 - SG LEVEL SETPOINTS A. SG LEVEL RULE i
Os s (s- ) 1.0 Any time the subcooling margin is lost, levels in the operable steam generators must be raised to 95% on the operating range using FW flow (MFW or EFW) through the uppe r nozzles in accordance with the FW throttling guidelines.
Exception: If the loss of subcooling margin was due to a loss of secondary steam pressure control or SG overfill, do not attempt to raise level in either steam generator until steam x pressure and level control is regained.
G' B. SG LEVEL GUIDELINES 1.0 F any RCPs are running, THEN maintain the low level limit of 30" on the startup range.
2.0 IF NO RCPs are running, THEN maintain 50% on the operate range, v
G V
Specific Rules DATE: 10-1-82 PAGE 70
BWNP-20007 (6-76)
BABCOCK & WILCOX Num ER NUCLEAR POWER GENERATION DIVl510N 74- 26473-00 TECHNICAL DOCUMENT SPECIFIC RULES AND/OR GUIDELINE 5 - RCP RESTART A. GUIDELINES FOR RCP RESTART AFTER RESTORING ADEQUATE SUBC00 LING MARGIN t
1.0 IF cooling with one or two SGs, THEN start one RCP per loop. IF, F unable to start a RCP in one loop, THEN start both RCPs in the opposite loop.
2.0 IF in the HPI cooling mode without SG cooling, THEN start only one RCP.
3.0 Restarting a RCP in the loop with the PZR spray is pre-
! ferred.
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O Specific Rules j D ATE :10-1-82 PAGE l
BWNP-20007 (6-76)
BABCOCK & WILCOX Numant
- f. NUCLEAR POWER GENERATION DIVl5lON 74-1126473-00
('\ jiTECHNICAL DOCUMENT SAD SECTION RCS Pressure and Inventory Control System SAD Dwg. No. Components Required to Support System e
f% i
,/ PZR Heaters EDS-0112-011-115 480V buses for heater banks and spray and Spray valve.
HPI EDS-0112-011-103 BWST, auxiliary building ventilation system, Decay Heat Closed Cycle Cool-ing System, Nuclear Services Closed Cycle Cooling System, 4160V and 480V buses for HPI pumps, 480V buses for
} motor-operated valves, 125V DC buses
\ / for ES switchgear breakers and valves, 120V AC bus to solenoid valves.
LPI EDS-0112-011-107 BWST, auxiliary building area coolers, Decay Heat Closed Cycle Cooling System, RB sump for LPI supply in recircula-tion mode , 4160V bus for LPI pumps, t
480V buses for LPI pumps and motor-l l
l
(] t operated valves and LHR pump area s% f coolers, 125V DC Suaes for ES switch-gear breakers.
I Chemical EDS-0112-011-016 Boric Acid Mix Tank, hydrazine drum, Addition caustic mix tank for sodium hydroxide ,
Boric Acid Storage Tank, lithium hydro-s xide storage tank, 480V buses for system component s , 120V AC buses for solenoid D valves.
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l SAD Section DATE: 10-1-82 PAGE 72
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BABCOCK & WILCOX NumsER NUCLEAR POWER GENERATION DIVl$10N 74-1126473-00 TECHNICAL DOCUMENT Secondary Heat Transfer Control System SAD Dwg. No. Components Required to Support System EHC EDS-0112-011-113 DC and AC power supplies for EHC con-trol,120V and 480V buses for EHC fluid pumps, Secondary Services Cooling Water system for EHC oil coolers, permanent magnet generator provides backup AC power to EHC cabinets, auto stop oil trip system.
Turbine EDS-0112-011-114 480V and 120V buses for turbine by-Bypass pass valves and valve controls ,
instrument air system supplies pneumatic valves.
Emergency EDS-0112-011-105 Condensate storage tank, condenser Feedwater hotwell supplies water when the condensate storage tank is depleted, 4160V bus to motor-driven EFW pump, 120V AC buses for controls of motor-operated valves, 480V buses to motor-operated valves, 125V DC panel to motor-operated valves and valve controls, 250V DC panel to motor-operated valves, SGs supply steam to EFW turbine-driven pump, intermediate building ventilation system, Nuclear Services Closed Cycle Cooling system.
O SAD Section PAGE 73 DATE: 10-1-82
BWNP-20007 (6-76)
BABCOCK & WILCOX Num ER NUCLEAR POWER GENERAflON OlVI$lON OCUMEMT 74-1126473-00 Reactor Building Control System SAD Dwg. No. Components Required to Support System RB Spray EDS-0112-011-104 4160V and 480V buses for RB spray pumps, 480V buses for valves, 125V DC buses for xN' / switchgear breaker, auxiliary building area coolers, Decay Heat Closed Cycle Cooling System, BWST, sodium hydroxide tank , RB sump.
RB EDS-0112-011-111 480V buses for fans, 125V DC buses Emergency for solenoid valves, Nuclear Services Cooling Closed Cycle Cooling System, Nuclear O
t j Service Seawater System.
\d RB EDS-0112-011-112 480V buses for motor-operated valves, Isolation 120V AC bus for solenoid valves, 125V DC bus for solenoid valves, k
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b SAD Section DATE: 10-1-82 PAGE 74
BWNP-20007 (6-76)
BABCOCK & WILCOX I NUCLEAR POWER GENERATION DIVI 560N O TECHNICAL DOCUMENT 74-1126473-00 SECTION ICC FOLLOWUP ACTIONS FOR INADEQUATE CORE COOLING 1.0 INITIATE HPI & LPI.
1.1 See Specific Rule 1.0.
1.2 E LPI is delivering flow, THEN maintain maximum LPI flow.
2.0 INCREASE SG LEVELS TO 90 - 95% ON THE OPERATE RANGE.
i 3.0 LOR SG PRESSURE TO INDUCE HEAT TRANSFER.
3.1 De pres surize SGs while maintaining levels to achieve secondary T-sat 90 to 110F lower than incore T/C tem-perature and maintain this AT.
i j 4.0 ENSURE CORE FLOOD TANK ISOLATION VALVES (CFV-5 AND CFV-6) ARE OPEN.
i j 5.0 g RC PRESSURE INCREASES TO 2300 PSIG, THEN OPEN THE PORV TO REDUCE j RC PRESSURE. RECLOSE WHEN RC PRESSURE FALLS TO 90 - 100 PSI ABOVE I
THE SECONDARY PRESSURE.
6.0 TAKE ACTION BASED ON FIGURE 3.
6.1 Average the five highest incore T/C temperature readings.
6.2 Determine which region of Figure 3 the RCS is in based on Step 6.1.
6.3 Using the region determined in Step 6.2, take action according to the following table.
Section ICC DATE: 10-1-82 PAGE 75
BWEP-20007 (6-76)
BABCOCK & WILCOX NumsER NUCLEAR POWER GENERATION DivlSION 74-1126473-00 TECHNICAL DOCUMENT REGION ACTION 1 Go to CP-103 2 Continue Step 1.0 through 5.0 above 3 Go to Step 7.0 4 Go to Step 12.0 O
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O Section ICC DATE: 10-1-82 PAGE 76 l
BWNP-20007 (6-76)
BABCOCK & WILCOX NumeER NUCLEAR POWER GENERATION DIYl510N 74- 126473-00 TECHNICAL DOCUMENT INCORE THERMOCOUPI.E TEMPERATURE IS IN REGION 3 7.0 START ONE RCP PER LOOP.
7.1 Do not override normal RCP interlocks.
8.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
8.1 Depressurize operating SGs as rapidly as possible to 400 psig or further if necessary to achieve a 100F decrease in secondary T-sat. SG pressure should not drop below the steam pressure necessary for the EFW pump turbine to deliver EFW, unless EFPT steam supply is available from Unit I or II.
9.0 OPEN ALL HIGH POINT VENTS.
, ( 10.0 E PRIMARY TO SECONDARY HEAT TRANSFER IS NOT ESTABLISHED, THEN OPEN THE PORV (RCV-10) AND GO TO CP-104.
10.1 Allow the RCS to depres sur ize until HPI/LPI/CFTs return incore thermocouple temperatures to saturation.
10.2 Go to CP-104.
11.0 E PRIMARY TO SECONDARY HEAT TRANSFER IS ESTABLISHED, THEN GO TO CP-103.
11.1 Maintain the primary to secondary heat transfer by cycling
( the PORV (RCV-10) to keep RCS pressure 25-50 psi greater than SG pressure.
11.2 GO TO CP-103.
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Section ICC DATE: 10-1-82 PAGE 77
BWNP-20007 (6-76)
BABCOCK & WILCOX NUMttR NUCitAR POWER GENERATION DIVISION 74-1126473-00 TECHNICAL DOCUMENT INCORE THERMOCOUPLE TEMPERATURE IS IN REGION 4 12.0 START ALL RCPs.
12.1 Starting interlocks shoul'd be defeated if necessary.
12.2 Do not defeat the overload trip circuit.
13.0 LOWER SG PRESSURE TO INDUCE HEAT TRANSFER.
13.1 Depressurize the operable SGs as quickly as possible to the minimum steam pressure necessary to power the turbine-driven EFW pump. IF stean supply to the EFPT is available from Unit I or II, THEN further depressurization is permitted.
14.0 OPEN ALL HIGH POINT VENTS.
15.0 DEPRESSURIZE THE RCS.
15.1 Open the PORV (RCV-10) AND PORV block valve (RCV-ll) and leave open.
15.2 Depressurize the RCS until CFTs and LPI restore core cooling.
j 16.0 WHEN INCORE THERMOCOUPLE TEMPERATURE RETURNS TO THE SATURATION TEM-PERATURE FOR THE EXISTING RCS PRESSURE , THEN CONTINUE WITH STEP 17.0.
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l DATE: 10-1-82 PAGE 78
BWNP-20007 (6-76)
BABCOCK & WILCOX wumste wucteAn rowen GENERADON DM$le a
(%.,) TECHNICAL DOCUMENT C00LDOWN FOLLOWING ICC (INCORE TEMPERATURES RETURNED TO SATURATION AFTER BEING IN REGION 4) 17.0 DECREASE RUNNING RCPs TO ONE PER LOOP.
[ } 18.0 MAINTAIN EFW FLOW.
( ,/ 18.1 _IF the motor-driven EFW pump is NOT available and the EFPT steau cannot be supplied by Unit I or II, THEN DO NOT reduce SG pressure below the minimum pressure necessary to power the EFPT.
19.0 WHEN LPI FLOW HAS BEEN IN EXCESS OF 1000 GPM IN EACH INJECTION LINE FOR AT LEAST 20 MINUTES, THEN STOP HPI PUMPS IF RUNNING AND CLOSE THE CFT ISOLATION VALVES. CONTINUE WITH 20.0, OTHERWISE, GO TO STEP j' 22.0.
V CAUTION DO NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY'THE ESAS WITH-OUT REVIEW OF THE POTENTIAL RELEASE OF RADIOACTIVE GAS OR LIQUID.
[N 20.0 TRANSFER LPI SUCTION TO RB SUMP.
k ,e 20.1 WHEN the BWST level drops to approximately 3 feet 9 inches or lo-lo-level alarms THEN trans fer LPI suc t ion to the RB sump as follows :
- b. Close DH-34 and 35, BWST to LFI pumps.
- c. Verify closed or close DHV-ll and 12, LPI discharge to MU pump suction.
I d. Close Sodium Hydroxide tanks discharge valves BSV-36 l /N and BSV-37.
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BWNP-20007 (6-76)
BABCOCK & WILCOX Nu= R E R NUCLEAR POWER GENERATION DIYlSloN 74-1126473-00 TECHNICAL DOCUMENT 21.0 CONTINUE LPI COOLING UNTIL FURTHER INSTRUCTIONS ARE GIVEN.
22.0 IF THE CONDITIONS OF STEP 19.0 ARE NOT MET BEFORE THE BWST LEVEL DROPS TO 3 FEET, 9 INCHES OR BWST ALARMS, THEN:
A) ALIGN ONE HPI PUMP TO TAKE SUCTION FROM THE RB SUMP USING THE LPI SYSTEM TO PROVIDE HPI PUhr SUCTION.
22.1 Place RB sump pumps to " Pull-to-Lock". Close WDV-3 and 4.
22.2 Open DHV-42 (43), RB sump valve.
22.3 Start or verify running DHP-1A (IB).
22.4 Open DHV-11 (12), LPI discharge to MU Pump suction.
22.5 Close DHV-34 (35), BWST to LPI pump.
22.6 Close MUV-58 (73), BWST to HPI pump.
22.7 Close NaOH Discharge Valves, BSV-36 and 37, 23.0 ESTABLISH CONDITIONS FOR LPI COOLING.
23.1 I_F, F primary temperature can be controlled by steaming the SG(s), THEN go to Step 23.4 otherwise continue.
23.2 Continue HPI/LPI " piggyback" mode until RCS presure is %250 psig.
23.3 Co to Step 23.7.
23.4 Cooldown the RCS by steaming the operable SGs while main-taining HPI/LPI flow until RCS pressure is %250 psig.
23.5 Throttle HPI flow to prevent exceeding limits of Figure 2.
23.6 Close the PORV (RCV-10) and cycle as necessary to maintain S 250 psig RCS pressure.
23.7 Maintain N250 psig and continue cooldown until adequate subcooling margin is established.
O Section ICC DATE: PAGE 80 10-1-82
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BWNP-20007 (6-76)
BABCOCK & WILCOX wuwen NUCtEAR POWER GENERADON DIYl$10N 74-1126473-00 TECHNICAL DOCUMENT ,
l 24.0 WHEN ADEQUATE SUBC00 LING MARGIN IS ATTAINED, THEN ESTABLISH LPI COOLING.
24.1 F two decay heat trains are operable, THEN go to Step l 24.5. IF, only one decay heat train is operable, THEN i
continue with Step 24.2.
24.2 WHEN the HPI/LPI piggyback operation has been supplying at least 1000 gpm to each loop for 20 minutes AND, during this 20 minutes the RCS pressure' has been less than the maximum pressure for LPI operation alone, THEN:
a) Verify that the LPI to RCS valve (DHV-5F or DHV-6F) is open.
l b) Establish normal MU to maintain seal injection.
c) Close LPI to HPI valves (DHV-11 and 12).
d) Close the CFT isolation valves.
24.3 WHEN two DHR systems ae operable , THEN follow Steps 24.5 -
24.7.
24.4 Un til two DHR systems are ope rab le , continue with Step 24.7.
CAUTION DO NOT ESTABLISH A FLOW PATH IN ANY SYSTEM ISOLATED BY THE ESAS WITHOUT REVIEW OF THE POTENTIAL RELEASE OF RADIO-1
( ACTIVE GAS OR LIQUID.
24.5 When two LPI pumps are operable , align one pump in DHR mode and continue operating the other pump in " piggyback" mode.
24.6 WHEN DH system flow has been greater than 1000 gpm in each line for at least 20 minutes, THEN f
Section ICC DATE: PAGE 81 10-1-82
BWMP-20007 (6-76) l i
BABCOCK & WILCOX NuxsER l NUCLEAR POWER GENERAftoN DIVISION TECHNICAL DOCUMENT 74-1126473-00 a) Trip RCP's, if running.
b) Terminate HPI.
! c) Establish both LPI sy, stems in DHR mode, d) Establish over pres sure protection by resetting the PORV setpoint.
e) Close the CFT isolation valves.
24.7 Maintain seal water flow to all RCP's in anticipation of immediate restart should LPI flow be interrupted (one RCP/ loop if required).
25.0 ESTABLISH LONG TERM COOLING PER CP-101.
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Figure 1 HPI FLOW VS. RC PRESSURE 1600 1500 -
1400 1300 -
THREE HPl PUMPS 1200 -
1100 -
1000 -
7=
5 900 -
B
=
800 - TWO HPl PUMPS
- E C
g 700 -
==
600 -
500 -
- 400 -
1 ONE HPl PUMP 300 -
200 -
100 -
l 0 i i ' ' !
500 1000 1500 2000 2500
- i RC System Pressure (psig) 74-1126473-00
I Figure 2 RC PRESSURE / TEMPERATURE LIMITS 2400 A0JUSIMENT FOR POS$lBLE IN5fRUMENTAfinN ERROR HAS BEEN CON 510ERED FOR THESE P.T Lluti CURWES.
2200 _
OPERATING CON 0lil0N ACCEPTABLE REGION 2000 ~ NO FORCIO FLCo- 11 ONLY iggg i REGION 1 _ REGION 11 1600
/ /
1400 b 1200 BRI TTLF.
2 FRACTURE
- NOT LlulTS l ADEQUATE 800 SUBC00 LING UNAtCEPTABLE maggig i
UNACCEPTABLE 400 200 /
100 200 300 400 500 600 700
' REFER 10 THE CURRENT CR 3 TECHNICAL SPECIFICAil0NS FOR RC Temperatur? ('F)
THESE NOT LluliS.
P 74-1126473-00 mt
Figure 3 CORE EXIT FLUID TEMPERATURE FOR INADEQUATE CORE C0OLING 2600 RC 2400 - f SUPERHEATED RC 2200 SUBCOOLE0 2000 -
1800 -
O REGION 1 REGION 2 REGION 3 1600 -
_i y 1400 -
I w y, 1200 -
g T M " CLA0 1000 -
=
& REGION 4 800 -
4 '
N N &
600 - 8 8
! 400 -
200 ' ' ' ' I I '
l 400 500 600 700 800 900 l
1000 1100 1200 1300 Core Exit Inermocouple Temperature (F) l I
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