ML19282B178
| ML19282B178 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1978 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19282B177 | List: |
| References | |
| NUDOCS 7903090217 | |
| Download: ML19282B178 (71) | |
Text
e e
STATISTICAL
SUMMARY
REPORT BRUNSWICK STEAM ELECTRIC PLAh"I - 1978 WHOLE BODY NO. OF INDIVIDUALS EXPOSURE RANGE (REM)
IN RANGE NONE MEASURABLE 885 LESS THAN 0.1 569 0.1 TO 0.25 200 0.25 TO 0.50 191 0.50 TO 0.75 95 0.75 TO 1.00 69 1
TO 2
167 2
TO 3
104 3
TO 4
45 4
TO 5
18
.5 TO 6
0 6
TO 7
0 7
TO 8
0 8
TO 9
0 9
TO 10 0
10 TO 11 0
11 TO 12 0
12 AND OVER 0
TOTAL 2343
J APPENDIX B STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION Number of Personnel ( > 100 mrem)
Total Man-Rem Station Utility Other Station Utility Other Wr~k & Job Function Employees Employees Workers Employees Employees Workers RenCTOR OPERATIONS & SUV.
Maintenance Personnel 0
0 13 0.653 0
14.663 Uperating Personnel 37 0
18 42.383 0
5.521 Healtn Fnysics Personnel 13 3
0 14.162 4.362 0
Supervisory Personnel 3
0 0
0.806 0
0 Engineering Personnel 12 0
10 6.705 0.030 8.364 ROUTINE MAINTENANCE Maintenance Personnel 44 0
114 54.259 0
151.358 Operating Personnel 1
0 0
1.803 0
0 Health Physics Personnel 5
3 0
3.693 2.762 0
Supervisorv Personnal 0
0 0
0.091 0
0 Engineering Personnel 5
0 4
2.526 0.054 3.004 INSERVICE INSPECTION Maintenance Personnel 0
0 0
0 0
0 Operating Fersonnel 0
0 0
0 0
0 Health Physics Personnel 0
0 0
0 0
0 Supervisorv Personnel 0
0 0
0 0
0 Engineering Personnel a
o R
1.444 0
5.558 SPECIAL MAINTENANCE Maintenance Personnel 40 30 283 50.469 16.203 324.046 Operating Personnel 4
0 0
9.440 0.368 0
Health Physics Personnel 9
4 12 8.309 4.437 7.520 Sn==rvisory Personnel 3
0 2
0.657 0
0.587 E-ueering Personnel 16 5
32 8.843 2.625 29.658 WASTE PROCESSING Maintenance Personnel 18 0
'98 24.579 0
131.324 Operating Personnel 27 0
0
-31.320 0
0 Health Physics Personnel 5
1 0
5.807 1.866 0
Supervisory Personnel O
O O
'O.105 0
0 Engineering Personnel 9
0 1
0.990 0.054 1.224 Decon Personnel REFUELING Maintenance Personnel 0
0 0
0 0
0 Operating Personnel 0
0 0
0 0
0 Health Pnysics Personnel 0
0 0
0 0
0 Supervisorv Personnel 0
0 0
0 0
0 Engineerinn Personnel 0
0 0
0 0
0 DECONNING Decon Personnel Health Physics Personnel TOTAL Maintenance Personnel 102 30 508 129.960 16.203 621.391 Operating Personnel 69 0
18 84.946 0
5.521 Health Physics Personnel 32 11 12 31.971 13.427 7.520 Supervisorv Personnel 6
0 2
1.659 0.368 0.587 EncMncerine Personnel 39 5
'55 22.508 2.763 47.808
[L 1 Personnel GRAND TOTAL 248 46 595 271.044 32.761 682.827 1.16.B.1
/
UNIT NO.
1 SAFETY RELATED PLANT NODIFICATIONS - 1978 F
TITLE / DESCRIPTION SAFETY ANALYSIS SP 0.
DA E NO.
REV.
78-9 5440 4-21-78 Addition of Ins'rumentation Pin Calibration instrument hookup is normally t
Jack to Facilitate CAC Drywell done by entering from the back of the moni-Gaseous, Iodine and Particulate tor cabinets. High voltage sources inside Monitor Calibration, the cabinet present a personnel safety hazard. A pin jack mounted outside the cabinet has eliminated the need to enter the cabinet for routine calibration and does not affect the operation of the monitor.
No No 78-23 4820 4-21-78 Drain Piping Modification to Air from the drywell is pumped to the moni-CAC Gaseous Monitors CAC-1259 &
tors for oxygen and hydrogen analysis. Due 1263.
to condensation in the sample line, it requires periodic draining. The original drain piping configuration was not adequate and modifications to increase draining capability have been completed, adding to the availability of this system.
No No 78-29 4623 3-15-78 Neutron Monitoring, Average A more conservative change to the APRM rod Power Range Monitor (APRM) block and reactor scram setpoints is re-Setpoint Change.
quired by the Standard Technical Specifica-tions. Lowering the setpoints because of instrument error increased the margin of safety for these instruments.
No No 78-59 4815 3-18-78 Automatic Depressurization Each relief valve tailpipe has a temperature System (ADS) Relief Valve Tail-sensor, which is used to indicate relief pipe Temperature Annunciator valve lifting or leaking. A temperature Setpoint Change, sensor alarm point of 200*F caused false alarms and was subsequently raised to 295'F as recommended by General Electric FDDR KBl-268, and in no way affects the operability of these valves.
No No
/
UNIT NO.
1 SAFETY RELATED PLANT h0DIFICATIONS - 1978 BSEP HDD.
COMPL.
TECH.
FILE FSAR NO.
DATE TITLE / DESCRIPTION SAFETY ANALYSIS SPEC.
NO.
REV.
REV.
78-65 4090 3-22-78 Removal & Temporary Storage of Building expansions require the removal of Security Television Tower &
this security television camera and tower.
Camera Number 8.
Camera number 2 will be used to monitor the plant entrance area, previously monitored by camera number 8.
No No 78-195 4820 9-8-78 CAC-1259 & 1263 Torus Sample High humidity sample air from the torus Line Rerouting for Improved condenses in the monitor sample lines, Condensation Drainage, resulting in unreliable monitor operation.
Sloping the line, where possible, tends to promote line self drainage and reduce monitor failures, therefore increasing monitor availability.
No No 78-220 5010 10-6-78 Simmer Margin Increase of Safety Inadvertant valve lif ting and leakage have Relief Valves.
caused undue operational events. Raising the lift setpoints 25 psi for each valve decreases the probability of inadvertant lifting. General Electric's Simmer Margin Analysis, NRC Review & License Amendment, and vendor laboratory relief valve setpoint adjustment were completed before the modification was installed. This modifica-tion required a change to the facilities FSAR.
(Reference NEOD-24138, Amendment No. 14.)
Yes Yes
/
UNIT NO.
1 SAFETY RELATED PLANT M0DIFICATIONS - 1978 BSEP HDD.
COMPL.
b FSAR NO.
DATE TITLE / DESCRIPTION SAFETY ANALYSIS NO.
REV*
REV.78-224 4628 10-6-78 Addition of Varistor to Ave. rage Weekly APRM Periodic Test,P.T. 1.1.7P, Power Range Monitor (APRM) K12 activates relays in the Reactor Protection Relay Coil to Suppress Noise System (RPS), which are located directly Induced on Main Steamline across from the Main Steamline Radiation.
Radiation Monitors, tionitors.
In order to suppress the relay actuerion induced noise, varistors were added across the APRM relay coils. A similar modification to this was installed in another operating plant. The varistors do not affect safe operation of the APRM relays.
No No
/
UNIT NO.
2 SAFETY RELATED PLANT HODIFICATIONS - 1978 H0D.
COMPL.
L FSAR NO.
DATE TITLE / DESCRIPTION SAFETY ANALYSIS NO.
REV*
REV.77-286 4821 6-13-78 HPCI & RCIC Leak Detection The mounting and wiring of the fif teen (15)
Temperature Switch Safety /
temperature switches weredone for personnel Accessibility Improvement, safety and accessibility. A terminal strip was introduced between the switch and field cables to allow easier calibration and repair and does not affect the operability of the system.
No No 77-399 4550 8-3-78 Recalibration of Reactor Water RWCU Leak Detection compares system outlet Cleanup (RWCU) Instruments Used flow to inlet flow.
If a difference exists, for Leak Detection, an indicated leak in the RWCU system will initiate isolation. A recalibration and setpoint change werecompleted to meet the requirement of the Technical Specifications.
No No 78-10 5440 4-21-78 Addition of Instrumentation Pin Calibration instrument hookup is normally Jack to Facilitate Radiation done by entering from the back of the Monitor Ratemeter Calibration, monitor cabinets. High voltage sources inside the cabinet present a personnel safety hazard. A pin Jack mounted outside the cabinet has eliminated the need to enter the cabinet for routine calibration without affecting the monitor operation.
No No 76-30 4623 3-16-78 Neutron Monitoring, Average A more conservative change to the APRM rod Power Range Monitor (APRM) block and reactor scram setpoints is re-Setpoint Change.
quired by the Standard Technical Specifica-tions.
Lowering the setpoints because of instrument error increased the margin of safety for these instruments.
No No
/
UNIT NO.
2 SAFETY RELATED PLANT HODIFICATIONS - 1978 BSEP HDD.
COMPL.
FILE FSAR NO.
DATE TITLE / DESCRIPTION SAFETY ANALYSIS C.
NO.
REV.
REV.
78-31 4540 6-20-78 Reactor Recirculation Pump Original thermal barrier design has resulted Thermal Barrier Replacement.
in several pump seal failures. The failures were caused by water leakage past the bar-rier (resulting in seal thermal shock) and barrier to stuffing box bolt failure. A redesigned thermal barrier was installed to prevent further seal and bolt failure.
Changes to the thermal barrier do not affect the safety of the Recirculation Pump or System.
No No 78-78 4820 4-12-78 Drain Piping Modifications to Air from the drywell is pumped to the CAC Gaseous Monitors CAC-1259 &
monitors for oxygen and hydrogen analysis.
1263.
Due to condensation in the sample line, it requires periodic dra'ining. The original drain piping configuration was not adequate and modifications to increase the draining capability increase the reliability of this system.
No No 78-178 4820 6-30-78 CAC-1259 & 1263 Torus Sample High humidity sample air from the torus Line Rerouting for Improved condenses in the monitor sample lines, Condensation Drainage, resulting in unreliable monitor operation.
Sloping the line, where possible, tends to promote self draining and reduce monitor failures, therefore increasing monitor availability.
No No
UNIT NO.
2 SAFETY RELATED PLANT MODIFICATIONS - 1978 10D.
COMPL.
TECil.
F1b F^
NO.
DATE TITLE / DESCRIPTION Se.?ETY ANALYSIS SPEC.
0-R REV.78-230 4623 9-22-78 Addition of Varistor to Average Weekly APRM Periodic Test, P.T. 1.1.7P, Power Range Monitor (APRM) K12 activates relays in the Reactor Protection Relay Coil to Suppress Noise Srstem (RPS), which are located directly Induced on Main Steamline across from the Main Steamline Radiation Radiation Monitors.
Monitors.
In order to suppress the relay actuation induced noise, varistors were added across the APRM relay coils. A similar modification to this was installed in another operating plant. The varistors do not affect safe operation of the APRM relays.
No No
TEST OR EXPERIMENT NOT DESCRIBED IN THE FSAR Title HPCI Overspeed Trip Test Date June 9, 1978 Description The purpose of this procedure is to test and document the automatic HPCI turbine overspeed trip.
Since the potential would exist to over-pressurize system piping by the HPCI pump if the overspeed trip does not actuate, the pump is uncoupled from the turbine at all times during the test.
Safety Analysis Normal HPCI turbine operating methods are used to bring the uncoupled turbine up to speed.
In case the automatic overspeed trip does not function, the turbine will be manually tripped.
This test does not affect the safe operation of the plant.
TEST OR EXPERIMENT NOT DESCRIBED IN THE FSAR Title Automatic Load Dispatch Date November 11, 1978 Description This procedure is designed to test the remote control Automatic Load Dispatcher.
Unit output is controlled by the dispatcher by varying recirculation pump speed.
Limitations to load changes are calculated and verification of manual overrides tested before a power change by the dispatcher is attempted.
Safety Analysis Power changes by varying recirculation pump flow are done routinely.
A control operator may take manual control back from the Automatic Load Dispatcher at any time and, therefore, this procedure does not constitute a safety concern.
TEST OR EXPERIMENT NOT DESCRIBED IN THE FSAR Title Transient Response With Loss of One of Two Circulating Water Pumps Date June 2, 1978 Description This test was performed to evaluate the effects of losing one out of two operating circulating water intake pumps during normal plant opera-tion.
The test could have resulted in a main turbine trip caused by low condenser vacuum.
The test was performed shortly before a scheduled shutdown.
However, condenser vacuum was maintained above the turbine trip setpoint and the plant was not affected by the test.
Safety Analysis This test could have only caused a main turbine trip, which is analyzed in the FSAR and hrs occurred during normal operation.
TEST OR EXPERIMENT NOT DESCRIBED IN THE FSAR Title HPCI Operational Hydrostatic Test Date April 21, 1978 Description On April 12, 1978, a HPCI system overpressurization was experienced when the turbine would not trip on overspeed (LER 1-78-39).
Visual inspection and Engineering analysis indicated that no permanent damage was done to the system as a result of overspeed and subsequent overpressurization.
This special test was devised to verify HPCI system piping integrity under design pressures.
Safety Analysis HPCI system piping integrity was verified by Engineering and QA during the special test.
Standard HPCI operating methods were used to pressur-ize system piping and verify its integrity.
This special test could in no way affect the operability or safety of the HPCI system.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 1-4-78 XII 5
MP 27 - ilandling the IF-300 Cask - Editorial changes.
1-4-78 X
10 PT 1.2.4 - APRM High Flux.& Downscale Test -
Revised to conform to Standard Technical Specifi-cations.
1-4-78 III 5
OP 26 EHC Hydraulic System - Editorial changen 1-4-78 III 4
OP 31 - Makeup Water Treatment System - Added
" Caustic Dilution Heater Thermostat" to chart (Page 21 of 30).
1-4-78 X
2 PT 3.1.21 - Recirculation Pump Discharge & Dis-charge Bypass Valve Operating Check - Revised to conform to Standard Technical Specifications.
1-4-78 X
8 PT 1.6.1 - Rod Sequence Control Systcm Opera-bility - Revised to conform to Standard Technical Specifications.
1-4-78 XVIII 17 Plant Notice 6 - Construction Work Control -
Delete.
1-4-78 I
5 PT 9.5 - HPCI 1000 PSIG Flow Rate Test - Added statement to close valve three seconds after opening.
1-4-78 IV 30 GP 1 - General Operating Procedure - Close Valve 2-E-41-F002 for three seconds after it has been fully opened.
1-4-78 III 13 OP 19 - High Pressure Coolant Injection System -
Close Valve 2-E41-F002 for three seconds after it has been fully opened.
1-6-78 X
8 PT 2.1.3P - HPCI Isolation Inst. (Steam Leak Det.) - Editorial changes.
1-6-78 X
21 PT 3.1.7P - Reactor Low Level #2 and #2 Channel Functional Test - Editorial changes.
1-6-78 X
9 PT 2.1.9P - RCIC Steam Leak Detection System -
Editorial changes.
1-6-78 X
14 PT 5.4P - Chloride Intrusion Monitors Channel Functional Test - Editorial changes.
1-6-78 X
5 PT 10.1.2 - RCIC Auto Act. & Logic Functional Test - Editorial changes.
1-6-78 X
16 PT 2.1.21P - Low Condenser Vacuum Channel Functional Test - Editorial changes.
OPERATING MANUAL PROCEDURE CHANCES 3
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE l-6-78 X
1 PT 45.2.16 - RWCU High Flow Response Time -
Editorial changes.
1-6-78 X
1 PT 45.1.3 - Reactor High Pressure Trip Response Time - Editorial changes.
1-6-78 X
4 PT 4.1.9 - A0G Process Rad. Monitoring -
Editorial changes.
1-6-78 X
19 PT 1.1.7P - APRM Flow Biased Neutron Trips Channel Functional Test - Editorial changes.
1-6-78 X
0 PT 1.1.13P - High Steamline Radiation Channel Alignment and Functional Test - Original issue in accordance with the Standard Technical Specifications.
1-6-78 X
0 PT 1.1.lPC - Reactor High Pressure Trip Channel Calibration and Functional Test -
Original issue in accordance with the Standard Technical Specifications.
1-18-78 X
17 PT 2.1.4P - Reactor Low Level #2 Channel Functional Test - Change from calibration to functional test.
1-18-78 X
25 PT 1.1.4P - Reactor Low Water Level #1 Channel Functional Test - Change from calibration to functional test.
1-18-78 X 13 PT 3.1.5P - Reactor Vessel Shroud Level Channel Functional Test - Change from calibration to
' functional test.
1-18-78 X
1 PT 2.1.27 - Groups 2, 6, 7, and 8 Logic System Functional Test - Editorial change on response time.
1-18-78' X 14 PT 2.1.17P - Steamline High Flow Channel Functional Test - Editorial change on response time.
1-18-7E X
1 PT 25.5P - Triaxial Time-History Accelographs Channel Check - Editorial change on response time.
1-184E X
7 PT 3.1.lP - LPCI Pump Discharge Pressure Inter-lock Channel Functional Test - Editorial change on response time.
1-18-7E X
1 PT 45.2.10 - Reactor Low Water Level #2 Response Time - Editorial. change on res,ponse time.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 1-18-78 X
l' PT 45.1.7 - Turbine Control Valve Fast Closure-Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.2.15 - Condenser Vacuum-Low Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.2.9 - High Steamline Radiation Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.1.5 - Main Steamline Isolation Valve -
Closure Circult Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.1.4 - Average Power Range Monitor Neutron Flux-High (15% and 120%) - Editorial change on response time.
1-18-78 X
1 PT 45.1.6 - Turbine Stop Valve-Closure Circuit Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.2.6 - Group 1 valves Isolation Circuit Response Time - Editorial change on response time.
1-18-78 X
1 PT 45.3.1 - High Drywell Pressure Response Time - Editorial change on response time 1-18-78 X 2
PT 2.1.20 - Group I Logic System Function _
Test - Revised to conform to Standard Technical Specification.
1-18-78 X
8 PT 8.1.2 - LPCI Simulated Automatic Actuation and Logic Functional Test - Revised to conform to Standard Technical Specification.
1-18-78 X 0
PT 3.1.2PC - CST Low Water Level Channel Calibration and Functional Test - Initial issue.
1-18-78 X 0
PT 2.1.17PC - Steamline High Flow Channel Calibration and Functional Test - Initial issue.
1-18-78 X 0
PT 3.1.6PC - CS, HFCI, LPCI High Drywell Pressure Channel Calibration and Functional Test - Initial issue.
1-27-7E X 0
PT 1.1.8PC - APRM Rod Blocks Channel Calibra-tion - Initial issue.
1-27-7E X
0 PT 1.2.3PC - APRM (15%) Neutron High Channel Calibration - Initial issue.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-1-78 III 11 OP 24 - Containment Atmospheric Control System-Allow for faster inerting with less operator supervision (LER l-77-102).
2-1-78 X
5 PT 1.10 - SRM & IRM Detection Position Rod Block Functional Test - Revised to conform to Standard Technical Specifications.
2-1-78 XVI 1
UA 23 5 Annunciator Procedures - Revised to give correct data.
2-1-78 XVI
-l UA 4 5 Annunciator Procedures - Editorial change.
2-1-78 XVI 1
UA 4 6 Annunciator Procedure - Editorial change.
2-1-78 X
l 4
PT 2.2.la - Primary Containment Isolation i
Valve - Editorial changes.
2-1-78 III 8
OP 32 Condensate Deep Bed Demineralizer System - Add new valve number.
2-1-78 X
4 PT 1.2.1 - Source Range Monitoring System -
Change Upscale and Rod Block Alarm Setpoint.
2-1-78 X
10 PT 12.2 - D/G Monthly Load Test - To ensure Fuel Oil Transfer Pump capacity does not drop below consumption rate.
2-1-78 N/A 0
STP 78 Initial issue.
2-1-78 XII 1
MP 24 - Flushing of Hot CRD Mechanisms -
Delete.
2-1-78 XII 2
MP 22 - Replacing Pressure & Exhaust Diaphragms on the CRD Scram Pilot Valves -
Delete.
2-1-78 X
6 PT 20.1P - Intake Canal Level Instrumentation -
Revised to conform to Standard Technical Specifications.
2-1-78 X
1 PT 1.1.4X - Reactor Low Water Level No. 1 Channel Functional Test - Revised to conform to Standard Technical Specifications.
2-1-78 X
1 PT 1.1.3X - High Drywell Pressure Channel Functional Test - Revised to conform to Standard Technical Specifications.
J
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-1-78 X
10 PT 2.1.23P - Reactor Vessel Pressure Shutdown Cooling Isolation - Revised to conform to Standard Technical Specifications.
2-1-78 X
14 PT 1.1.3P - High Drywell Pressure Channel Functional Test - Revised co conform to Standard Technical Specifications.
2-1-78 X
1 PT 45.2.8 - High Drywell Pressure Response Time - Editorial changes.
2-1-78 X
2 PT 45.2.7 - Reactor Low Water Level #1 Response Time - Editorial changes.
2-1-78 X
2 PT 45.3.5 - LPCI Initiation Response Time -
Editorial changes.
2-1-78 X
3 PT 45.3.3 - Core Spray Initiation Response Time - Editorial changes.
2-1-78 X
1 PT 45.3.2 - Reactor Low Water Level No. 2 and No. 3 - Editorial changes.
2-1-78 X
1 PT 45.2.14 - HPCI Steamline High Differential Pressure Response Time - Editorial changes.
2-1-78 X
2 PT 45.2.16 - Reactor Water Cleanup High Flow Response Time - Editorial changes.
2-1-78 X
2 PT 45.2.1 - Main Steamline Tunnel Temperature Switch Response Time - Editorial changes.
2-1-78 X
1 PT 45.2.2 - Reactor Water Cleanup Area High Temperature Response Time - Editorial changes.
2-1-78 X
10 PT 1.5.2P - IRM Rod Blocks - Editorial changes.
2-1-78 X
22 PT 3.1.7P - Reactor Low Water Level #2 and
- 3 Channel Functional Test - Delete use of pneumatic calibrator and change valving procedure to allow plant pressure to actuate instrument.
2-1-78 X
1 PT 1.1.13P - High Steamline Radiation Channel Alignment and Functional Test - Added additional "As Found/As Left" blocks for channels B,C, and D.
2-1-78 X
7 PT 3.1.12P - Core Spray Pump Discharge Interlock Channel Functional Test - Added " Sound Powered Phone" to equipment list.
/
OPERATING MANUAL PROCEDURE CHANCES DATE VOL.
'O.
NUMBER & TITLE / CHANGE 2-1-78 X
14 PT 2.1.2P - HPCI Turbine Steamline Low Pressure Channel Functional Test - Added
' Initial' sign-off blanks for step U.
2-1-78 X
2 PT 46.3P - Control Building Chlorine Detection System - Step 'A'
- Added ' Initial' sign-off blank for both units.
Step 'B' - Deleted
' Initial' sign-off blank for Unit No. 2.
2-1-78 X
0 PT 3.1.lPC - LPCI Pump Discharge Pressure Interlock Channel Calibration and Functional Test - Initial issue.
2-1-78 X
0 PT 1.1.3PC - High Drywell Pressure Channel Calibration and Functional Test - Initial issue.
2-1-78 X
0 PT 1.1.3XC - High Drywell Pressure Channel Calibration and Functional Test - Initial issue.
2-1-78 X
0 PT 3.1.14PC - Reactor Low Pressure Channel Calibration and Functional Test - Initial issue.
2-1-78 X
0 PT 3.1.14XC - Reactor Low Pressure Channel Calibration and Functional Test - Initial issue.
2-1-78 X
0 PT 2.1.26PC - Main Steanline Low Pressure Channel Calibration and Functional Test -
Initial issue.
2-1-78 I
O PT 3.1.7PC - Reactor Low Water Level #2 and
- 3 Channel Calibration and Functional Test -
Initial issue.
2-8-78 XVII 3
BSEP Industrial Security Plan - Revised to conform to amendment to 10 CFR73.55.
2-8-78 XVII 16 SI 9 - Access Control and Personnel Identification - Revised to conform to BSEP Industrial Security Plan.
2-8-78 IV 6
OG 3 - Primary Containment Access Control -
Change Item 2 to ensure Primary Containment Atmosphere is 18% 0xygen prior to entry.
2-8-7E IV 32 GP 1 - General Operating Procedure - Revised to conform to Standard Technical Specifications..
2-9-7E XVIII C
PN 18 - Special Work Authorization - Initial issue.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-9-78 XX 3
ENP 3 - Implementing Instructions for Plant Modifications - Editorial changes.
2-17-78 X
0 PT 7.1.7PC - Core Spray - Initial issue.
2-17-78 X
0 PT 2.1.7PC - HPCI Turbine Exhaust Diaphragm High Pressure Channel Calibration and Functional Test - Initial issue.
2-17-78 X
1 PT 3.1.7PC - Rx Low Water Level #2 and #3 Channel Calibration Test - To correct switch numbers.
2-17-78 X
0 PT 3.1.12PC - Emergency Core Cooling System -
Initial issue.
2-17-78 VIII 16 Radiation Control and Test Procedure 0002 -
Raw lubricating oil analysis, fire pump for fuel oil storage, and Aux. Boiler pH and Alkalinity.
2-22-78 X
9 OP 1.6.1 - Rod Sequence Control System Operability - Editorial change.
2-22-78 X
4 PT 2.3.1 - Drywell to Suppression Chamber Vacuum Breakers - Exercise Vacuum Breakers Limit Switches as required in LER 78-4.
Action to prevent reoccurrence.
2-22-78 X
4 PT 1.5.6 - APRM Upscale '(Flow Biased) & Down-scale - Editorial changes.
2-22-78 X
7 PT 1.2.3 - Average Power Range Monitor (15%) -
Revised to conform to Standard Technical Specifications.
2-22-78 III 2
OP 27 - Generator and Exciter System - Update Unit No. 2 Electrical Lineup Sheet.
2-22-78 X
11 PT 12.2 - D/G Monthly Load Test - Converted into four (4) separate PT's.
Revised to conform to Standard Technical Specifications.
2-22-78 III 16 OP 2 - Reactor Recirculation System - Include in OP 2 a section for filling and venting the pump casing and seal system.
2-22-78 X
0 PT 12.2a - No. 1 D/G Monthly Load Test -Initial issue.
2-22-78 X
0 PT 12.2b - No. 2 D/G Monthly Load Test - Initial issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-22-78 X
0 PT 12.2c - No. 3 D/G Monthly Load Test - Initial issue.
2-22-78 X
0 PT 12.2d - No. 4 D/G Monthly Load Test - Initial issue.
2-23-78 X
1 PT 1.1.8PC - APRM Rod Blockc Channel Calibration-Adding note to clarify acceptance criteria.
2-23-78 X
1 PT 1.2.3PC - APRM 15% Channel Calibration -
Adding note to clarify acceptance criteria,and editorial changes.
2-23-78 X
10 PT 1.5.3P - SRM Rod Blocks Channel Functional Test - To cover in the FREQUENCY paragraph the condition of going from RUN to S/U and to include in the PURPOSE paragraph the appropriate TECH. SPEC. table.
2-23-78 X
1 PT 45.2.5 - Vent Air Inlet / Outlet High Differential Temperature Response Time -
Editorial changes.
2-23-78 X
1 PT 45.2.4 - Reactor Building Exhaust High Radiation Response Time - Editorial changes.
2-23-78 X
1 PT 2.1.12PC - RCIC Steamline High Differential Pressure Channel Calibration and Functional Test - Adding blank for " Unit No." in title and removed word " Level" from calibration check.
2-23-78 X
1 PT 2.1.17PC - Steamline High Flow Channel Calibration ano Functional Test - Added state-ment in acceptance criteria for indication, added steps to check A71-K3C and K3D contacts, and added tolerance for indicators on four data sheets.
2-23-78 X
1 PT 3.1.2PC - Condensate Storage Tank Low Water Level Channel' Calibration and Functional Test -
Editorial changes.
2-23-78 X
15 PT 5.4P - Chloride Intrusion Monitors Channel Functional Test - Added note to explain operation of annunciators L and J to prevent any confusion during performance of PT.
2-23-78 X
17 PT 1.1.12P - High Steamline Radiatioa Channel Functional Test - Added " Reset Annunciators" to step 7 as a reminder to operator, and editorial changes.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-23-78 X
0 PT 2.1.1PC - HPCI Steamline High Differential Pressure Channel Calibration and Functional Test - Initial issue.
2-23-78 X
0 PT 1.1.4XC - Reactor Low Water Level No. 1 Channel Calibration and Functional Test -
Initial issue.
2-23-78 X
20 PT 1.1.7P - APRM High (fixed) and Flow Biased (thermal) Neutron Trips Channel Functional Test - To include steps to check APRM Flux High prior to S/U to cover Tech. Spec. Table 4.3.1-1, paragraph 2.c, plus editorial changes.
2-23-78 X
0 PT 1.1.4PC - Reactor Low Water Level No.1 Channel Calibration and Functional Test - Initial issue.
3-1-78 X
5 PT 1.5.4 - Control Rod Block Subtest:
For APRM Inop. & Upscale (12%) - To reflect surveillance requirements of Standard Tech. Specs.
3-1-78 III 5
OP 31 - Ebkeup Water Treatment System - Added in-line strainer information.
3-1-78 X
3 PT 46.1 - Locked Valves - Allow spectacle flanges on reactor feed pump turbine oil reservoirs to be in the open position.
3-1-78 X
8 PT 13.1 - Reactor Recirculation Loops / Jet Pump Operability - Add new graphs for 2A and 2B pumps (curves 3 & 4).
Delete old curves.
3-1-78 X
1 PT 45.2.13 - HPCI Steamline Low Pressure Response Time - Allow PT to be run with Plant not in shutdown.
Chart speed and ID-100 pressure changes for better ramp rates.
3-1-78 X
2 PT 16.1 - CAD System Performance - To meet Standard Tech. Specs. frequency requirement and correct Tech. Spec. reference.
Editorial changes.
3-1-78 X
5 PT 1.2.2 - Intermediate Range Monitor - To meet Tech. Spec. frequency requirement.
3-1-78 X
1 PT 45.2.11 - Main Steamline Low Pressure Response Time - To allow performance of PT with Plant operating. Corrections required due to Plant Mod and Recorder Chart Speed and ID-100 Pressure changes.
3-1-78 VIII 9
Radiation Control and Protection Manual - Editor-ial changes.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 3-1-78 N/A 1
SIP 78 Reconfiguration of IF-300 Cask -
Change torque valves.
3-1-78 X
0 PT 2.1.4PC - Reactor Low Water #2 Channel Calibration and Functio ~nal Test - New PT required by Standard Tech. Specs.
3-1-78 X
0 PT 35.12.4 - Recirculation Motor - Generator Sets Deluge Systems - New PT developed to satisfy insurance requirements.
3-1-78 X
0.
PT 35.~12.6 - Reactor Feedwater Pump Deluge System - New PT written to satisfy insurance requirements.
3-1-78 X
0 PT 35.12.5 - Hydrogen Seal Oil Deluge System -
New PT for testing H Seal Oil System per 2
insurance requirements.
3-1-78 X
0 PT 35.17 - Fire Detection System - To bring PT into compliance with as-built systems.
3-1-78 I
O PT 35.4.3 - Fire Detection System - New PT replacing deleted PT 35.4.
Provides better control and clearer instructions for performing the test.
3-1-78 X
0 PT 1.5PC - Rod Block Monitor Channel Calibration-To comply with Standard Tech. Specs.
3-3-78 X
0 PT 2.1.5PC - RCIC Turbine Steamline Low Pressure Calibration and Channel Function Test - New PT required by Standard Tech. Specs.
3-1-78 X
15 PT 2.1.17P - Steamline High Flow Channel Functional Test - Editorial changes.
3-1-78 X
9 PT 2.1.3P - HPCI Steam Leak Detection System -
Editorial changes.
3-1-78 X
1 PT 3.1.5PC - Reactor Vessel Shroud Level Channel Calibration - Changed to comply with Standard Tech. Specs., and editorial changes.
3-1-78 X
0 ENP 5 - Cable Pull Slip Form Documentation -
Provides for Cable Pull Slip Documentation Control.
3-1-78 X
12 PT 2.1.5P - RCIC Turbine Steamline Low Pressure Channel Functional Test - Editorial changes.
3-1-78 X
1 PT 45.2.3 - HPCI Steamline Tunnel Temperature -
High (Response Time) - Added a calibration reauirement, and editorial changes.
OPERATING MANUAL PROCEDURE CHANCES t
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 3-8-78 VIII 3
RC&T Procedure 0008 - Radioactive Liquid Effluent Releases and Reports - To allow releases of very low activity to be made when rad. monitor is out of service or release is from a point that cannot be sent through rad.
monitor.
3-9-78 X
2 PT 25.2P - Seismic Monitor System - Editorial changes.
3-9-78 X
0 PT 55.lPC - Drywell Pressure Loop Calibration -
Initial issue.
3-9-78 X
21 PT 1.1.7P - APRM Neutron, Thermal and Rod Block Trips - Incorporate Operations PT 1.5.6 APRM Flow Biased UPSC and DNSC; removed set-point verification feature in steps and Table I.
Editorial changes.
3-9-78 X
0 PT 2.1.9PC - RCIC Steam Leak Detection System Channel Calibration and Functional Test - Initial issue.
3-9-78 X
2 PT 1.2.3PC - APRM (15%) Channel Calibration -
Reduced setpoint for APRM Startup trip from 15% (1.20 volts) to 14, 1 5% (1.12, tD.04 volts) as per Plant Mod.78-030.
>15% is Tech. Spec.
reportable.
3-9-78 X
2 PT 1.1.8PC - APRM Rod Blocks Channel Calibration - Reduced setpoint for APRM Startup Rod Block from 12% (0.96 volts) to 11, 1 5%
(0.88, fp.04 volts) as per Plant Mod.78-030.
>l2% is Tech. Spec. reportable.
3-9-78 X
0 PT 12.6 - Electrical Power Systems Breaker Alignment Surveillance - Editorial changes.
3-9-78 III 4
OP 39 - Diesel Generator - To include in the procedure the possible causes of a D/G not returning to the Standby Condition when shut down and the indications available to the operator to assure it is in the Standby Condition.
3-13-78 KVIII 1
PN 18 - Special Work Authorization - Change to distribution.
3-13-78 X
1 PT 50.5 - Total Core Flow Calibration -
Editorial changes.
3-13-78 X
3 PT 1.8D - Core Thermal Power Calculation -
Editorial changes, and blank for recording DVM Serial Number.
OPERATING MANUAL PROCEDURE C1WICES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIWIGE 3-13-78 X
1 PT 1.8C - Hand Calculation of AGAF's -
Added standard PT sign-off sheet.
}-13-78 X
6 PT 6.1 - Standby Liquid' Control System Component Test - Editorial changes.
3-13-78 X
4 PT 7.2.1.- Core Spray System Component Test -
Editorial changes, and flow path verification.
3-13-78 IV 33 GP 1 - General Operating Procedure - Add new sequence for fuel Cycle 2.
3-20-78 XII O
le 29 - Maintenance Procedure - Initial issue.
3-20-78 X
16 PT 5.4P - Chloride Intrusion Monitors Channel Functional Test - Adding note to change reportability to include annunciators and also to be applicable only to acceptance criteria A, B, C, a D.
3-20-78 X
1 PT 2.1.4PC-Reactor Low Water Level #2 Channel Calibration and Functional Test - Corrected to allow testing switch #4 - incorrect terminals were listed for checking switch #4.
3-20-78 X
0 PT 2.1.3PC - Steam Leak Detection System Calibration and Channel Functional Test -
Initial issue.
3-20-78 X
11 PT 1.5.2P - IRM Rod Blocks - Delete steps to lower the high voltage and pull module when checking INOP circuit.
3-20-78 X
1 PT 3.1.14XC - Reactor Low Pressure Channel Calibration and Functional Test - Due to error in Standard Technical Specifications, Rev. O was written with the wrong setpoint. Tech.
Spec. is being revised.
3-20-78 X
11 PT 1.5.3P - SRM Rod Blocks Channel Functional Test - For an adequate check of the INOP circuit, it was not felt necessary to do the additional steps for lowering the high voltage, and pulling a plug-in module; therefore, the associated steps are being deleted.
3-22-7E X
1 PT 45.1 - Loading Dock Transfer Lines Hydro PT -
Typographical error - valve positions were reversed.
3-22-78 X
5 PT 1.5.6 - Control Rod Blocks - Delete. Has been included in PT 1.1.7P.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 3-22-78 X
1 PT 33.1 - EHC Accumulator Precharge - Editorial changes.
3-22-78 X
1 PT 20.2 - Main Steam Isolation Valves Leakage Rate Testing - Delete'.
3-22-78 X
0 PT 25.12.2 - Diesel Generator Deluge System -
Initial issue.
3-22-78 X
2 PT 7.1.8 - Core Spray System Component Test -
Format change to conform to ISI procedures.
Also, to delete the System Check List and Oc include Flow Path Verification as required.y ISI.
3-22-78 X
5 PT 7.2.1 - Pump Flow Rate, Core Spray - This revision is identical to revision 3.
Revision 4 was inadvertently made to this procedure instead of PT 7.1.8.
3-22-78 X
2 PT 10.1.la - RCIC System Component Test -
Format changes to bring this PT in line with other ISI procedures.
Also, to delete the System Check List and to include Flow Path Verification as required by ISI.
3-22-78 X
5 PT 8.2.4 - RHR Service Water System Component Test - To delete pump and valve operability.
These will be included in PT 8.1.4.
Also, to add Flow Path Verification.
3-22-78 X
0 PT 12.0 - Diesel Generator Service Water System Component Test - Initial issue.
3-22-78 X
3 PT 9.3.a - HPCI System Component Test - Format change to bring this PT in line with other ISI procedures. Also, to include the Flow Path Verification as required by ISI.
3-22-78 X
6 PT 8.1.3 - LPCI/RHR System Component Test -
Format change to bring this PT in line with other ISI procedures. Also, to delete the System Check List and to include Flow Path Verification as required by ISI.
3-22-78 IX 0
FH 15 - Loading and Unloading the.IF-300 Spent Fuel Cask With BWR Fuel - Initial issue.
3-22-78 X
0 PT 24.0 - Service Water - Initial issue.
3-24-78 X
0 PT 55.2PC - Reactor Pressure Loop Calibration -
New procedure required by Standard Tech. Specs.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 3-24-78 X
0 PT 55.3PC - Reactor Vessel Level Loop Calibration - New procedure required by Standard Tech. Specs.
3-24-78 X
1 PT 2.1.9PC - Steam Leak Detection System Channel Calibration and Functional Test -
To correct a setting listed in the acceptance criteria. To remove test equipment not required.
Editorial changes.
3-31-72 X
3 PT 3.1.21 - Reactor Coolant Recirculation System - Rewritten completely to bring into line with ISI Pump & Valve Program.
3-31-78 X
0 PT 3.1.22 - Reactor Coolant Recirculation System - New procedure required by ISI Pump &
Valve Program.
3-31-72 X
3 PT 16.1 - Containment Atmospheric Dilution System - Rewritten to bring into line with ISI Pump & Valve Program.
3-31-7E X
0 PT 25.1 - Nuclear Steam Supply - New procedure required by ISI Pump & Valve Program.
4-3-78 I
O PT 35.4.4 - Fire Detection System - Initial issue.
4-3-78 X
3 PT 7.1.8 - Core Spray System Component Test -
Editorial change.
4-3-78 X
6 PT 7.2.3 - Core Spray System - Revised to include testing required by ISI.
4-3-78 IX 0
FH 14 - On-Site Transfer of Spent Fuel -
Initial issue.
4-3-78 XVI 1
UA 13 (2-4) - Generator Field Over Excitation -
Add note under device /setpoints to explain how to reset the annunciator after the cause of the overexcitation has been corrected.
4-3-78 III 4
OP 27 Generator Gas - Add precaution to shut H, detraining float valve bypass'H-05 prior Eo pressurizing generator above 8 psig.
4-3-78 XVI 2
UA 6, 1-2 Gen. Bus Under Freq. - Load reject at >30% first STU Shell Pressure will cause Rx scram since select rod insert and 200 msee time delay is no longer in use.
4-3-78 VI 6
EI 36 - Low System Frequency - Editorial change.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-3-78 XVI 1
A 3, 1-1 (Unit No. 1) Safety or Depress Valve Leaking - Incorporate changes in Alarm Setpoint, and reference GE letter concerning Suppression Pool Temp. Transients..
4-3-78 XVI 2
A 3,1-1 (Unit No. 2) Safety or Depress Valve Leaking - Incorporate changes in Alarm Setpoints, and reference GE letter concerning Suppression Pool Tecp. Transients.
4-3-78 I
25 OM 1 - Administrative Procedures - Revised to route PT's to QA prior to sending to vault.
4-3-78 X
6 PT 1.2.2 - Intermediate Range Monitor -
Editorial changes.
4-6-78 IV 34 GP 1 - General Operating Procedure - To incorporate as permanent revisions the temporary revisions of 3-23-78 and 3-25-78 tc Appendix 2-B-1.
4-6-78 X
1 MP 29 - Handling the IF-300 Cask Transporting BWR Fuel from Unit No. 2 to Unit No. 1 -
f Editorial changes.
4-6-78 X
1 PT 1.1.7PC APRM - Fixed and Flow Biased (Thermal)
Neutron Trips Channel Calibration - Editorial changes, and change setpoints of 15% and 12% to 14% and 11%.
4-6-78 X
10 PT 1.1.2P - Reactor Protection Instrument Test -
Added jumper to " Test Equipment Recommended" and removed steps for valving operations on vent valves.
4-6-78 X
1 PT 45.2.12 - PCIS (Group I Logic) - Combined with PT 45.2.12A, to allow PT to be performed with plant operating, to use test jacks for connection points and to change ID-100 pressures and recorder chart speeds for better test result.
4-6-78 X
1 PT 45.2.12A - Main Steamlina High Flow Response Time - Delete.
4-6-78 X
1 PT 55.3 - Reactor Vessel Level Loop Calibration -
Typing error and switch location.
4-6-78 X
1 PT 3.1.12PC - Emergency Core Cooling System -
Added initial sign-off blanks.
4-6-78 X
1 PT 2.1.26PC - Primary Containment Isolation System - Add Table I for jumper locations.
O_PERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-6-78 X
1 PT 3.1.11PC - Emergency Core Cooling System -
Editorial change.
4-6-78 X
9 PT 2.1.8P RCIC - Editorial change.
4-6-78 X
12 PT 3.1.llP - Emergency Core Cooling System -
Added flange gasket part number and replace-ment step because of new venting procedures.
Revised Figure 1 to reflect recent changes to level instrumentation.
4-6-78 X
13 PT 2.1.5P - RCIC - Changed equipment required from 100 psig gauge to 400 psig gauge to correct typo.
4-6-78 X
14 PT 1.1.1P - Reactor Protection Test - Changed equipment list from " Required" to " Recommended."
4-6-78 X
2 PT 3.1.14XC - Emergency Core Cooling System -
Revised to show correct switch number (#2).
4-6-78 X
0 PT 41.2 - Inspection of Crane Hooks, Crane Brakes, Ropes and Chains - Initial issue.
4-6-78 X
2 PT 2.1.9PC - Steam Leak Detection System Channel Calibration and Functional Test -
Editorial change.
4-6-78 IX 1
FH 15 - Loading and Unloading the IF-300 Spent Fuel Cask With BWR Fuel - Editorial changes.
4-6-78 X
4 PT 8.1.4 - RHR Service Water System Component Test - To bring within requirements of ISI as required by Tech. Specs.
4-7-78 X
4 ENP 3 - Q-List Modification Procedure -
Editorial changes.
4-7-78 X
10 PT 2.1.3P - HPCI Isolation Instrumentation Steam Leak Detection System - To rese.t HPCI Isolation Trip Signal A so that Turbine Trip Solenoid logic, and annunciator, can be checked when performing test on the B Logic Trip system.
4-7-78 III 8
OP 6 - Radwaste - To reflect valve and piping changes associated with FECP 1507 (Additional Release Monitor) and PM 77-332 (Flushing Line Modification).
4-7-78 VI O
EI 45 - Explosion in Off Gas Piping and Filter House - Initial issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-7-78 X
5 PT 1.2.1 - Source Range Monitoring System -
Update for clarity and add requirements of Technical Specifications Section 9.2.6.
4-12-7E XI 2
FH 15 - Loading and Unioading the IF-300 Spent Fuel Cask with BWR Fuel - Reassign locations of spent fue.1 assemblies in the Unit No.1 pool.
4-12-7E X
1 PT 2.1.3PC - HPCI Isolation Instrumentation -
The temperature stated in VII.
K.,
step 9, that the module should trip at, should be 165, 16*F, not 190, 16*F.
The temperature stated in Section VII.
M., steps 2 and 3 should be 165, 16*F, not 190, 16'F.
4-19-7E XII 2
MP 29 - Handling the IF-300 Cask Transporting BWR Fuel from Unit No. 2 to Unit No. 1 - To allow use of manual torque wrenches, to include steps for performing radiation surveys and to incorporate temporary revision dated 4-8-78.
4-19-7E X
N/A PT 19 6.2 - Inspection of BOP Snubbers - Delete.
4-19-78 X
N/A PT 19.6.0 - External Inspection of Snubbers on Safety Related Systems - Delete.
4-19-78 X
2 PT 3.1.2PC - Emergency Core Cooling System -
Steps D and 0 revised to include differences in instrument numbers between Unit Nos. 1 and 2.
All other steps listed changed valving procedure which should allow more accurate determination of reset point by forcing air out of instrument.
4-19-78 X
1 PT 41.2 - Inspection of Crane Hooks, Crane Brakes, Ropes & Chains - :Taximum hook throat opening should read 15% vice 15*.
Added " Hook Crack" inspection checkoff.
4-1948 XII N/A le 5 - Repair and Testing of Relief Valves -
Delete.
4-19-78 X
16 PT 2.1.17P - Steamline High Flow Channel Functional Test - Revisions to allow plant pressure to actuate the instrument when plant is pressurized to >300 psig.
4-19-78 X
2 PT 3.1.5PC - Reactor Vessel Shroud Level Channel Calibration - Editorial changes.
4-19-7E I
O PT 1.2.lA - Source Range Monitoring System -
Initial issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIWIGE 4-19-78 III 12' OP 24 - Containment Atmospheric Control System 4-19-78 X
N/A PT 30.1 - Sanitary Waste Treatment - Delete.
4-19-78 X
N/A PT 7.2.1 - Core Spray - Pump Flow Rate -
Delete.
4-19-78 X
1 PT 12.2c - No. 3 D/G Monthly Load Test - Sign-off page to include "PT Exception Form is Attached", and editorial changes.
4-19-78 X
1 PT 12.2b - No. 2 D/G Monthly Load Test - Sign-off page to include "PT Exception Form is Attached", and editorial changes.
4-19-79 X
1 PT 12.2a - No. 1 D/G Monthly Load Test - Sign-off page to include "PT Exception Form is Attached", and editorial changes.
4-19-78 X
2 PT 8.2.2a - RHR Unit Coolers Operability -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
4 PT 1.1.11 - Reactor Mode Switch (C72A-S1) in Shutdown - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 1.2.4a - APRM INOP - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 37.2.2 - Reactor Feedpump Turbine Stop Valve Test - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
4 PT 3.1.21 - Reactor Coolant Recirculation System - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 37.1 - Reactor Feedpump Turbine Overspeed Check - Sign-off page to include "PT Exception Form is Attached."
4-19-70 X
3 PT 40.2.2 - Automatic Pump Starts - Sign-off page to include "PT Exception Form is Attached."
4-19-7E X
3 PT 35.1 - Fire Protection System '- Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
3 PT 37.2.3 - Reactor Feedpump Turbine Thrust Bearing Wear Test - Sign'off page to include "PT Exception Form is Attached."
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-19-78 X
5 PT 15.6 - Standby Gas Treatment Operability -
Sign-off page to include "PT Exception "orm is Attached."
4-19-78 X
6 PT 4.1.8 - Of f-Gas Hi Rad. Operability Check -
Sign-off page to include "PT Exception Form is Attached. ','
4-19-78 X
2 PT 5. 2 - Sump Pu=ps/ Coolers Operability Test -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
5 PT 2.2.2 - Primary Containment Isolation Valves (2) (MSIV'S) - Sign-off page to include "PT Exception Form is Attachad."
4-19-78 X
8 PT 1.5.1 - Rod Block Monitor - Sign-off page to include "PT Exception Form is Attached."
4-19-78 T.
6 PT 1.2.1 - Source Range Monitoring System -
Sign-off page to include "PT Excep' tion Form is Attached."
4-19-78 X
11 PT 1.2.4 - APRM High Flux & Downscale Test -
Sigp-off page to include "PT Exception Form is Attached."
4-19-78 X
4 PT 1.1.6 - Reactor Protection Instrument Check -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
3 PT 33.2 - Testing Standby EHC Pump - Sign-off page to include "PT Exception Form is Attached."
l 4-19-78 X
1 PT 36.4A - Stator Cooling - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 2.2.3 - Primary Containment Isolation Valves Closure Timing - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
12 PT 40.2.5 - Turbine Control Valve Testing -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 40.2.6 - Turbine Overspeed Trip Test -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 45.1 - Loading Dock Transfer Lines Hydro PT -
Sign-off page to include "PT Exception Form is Attached."
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-19-78 X
4 PT 46.1 - Locked Valves - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
7 PT 18.1 - Refueling Interlock Check - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 18.2 - Service Platform Interlock Check -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
5 PT 23.1 - Control Building HVAC Systems -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 33.1 - EHC Accumulator Precharge - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 34.1 - Auxiliary Boiler System - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
3 PT 36.1 - Stator Cooling System - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 37.2.1 - Reactor Feedpump Turbine Governor and Trip Mechanism Test - Sign-off page to in-clude "PT Exception Form is Attached."
4-19-78 X
2 PT 12.2.1 - ECCS D/G Logic Test - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 12.6 - Breaker Alignment Surveillance -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
9 PT 13.1 - Reactor Recire. Loops / Jet Pump Operability - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
9 PT 14.1 - Control Rod Operability Check -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
6 PT 15.4-Secondary Containment Integrity - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 15.4a - Secondary Containment Integrity -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
5 PT 2.3.1 - Drywell to Suppression Chamber Vacuum Breakers - Siga-off page to include "PT Exception Form is Attached."
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-19-78 X
3 PT 2.3.2 - Reactor Building to Torus Vacuum Breakers - Sign-off page tc include "PT Exception Form is Attached."
4-19-78 X
7 PT 4.1.1 - Reactor Building Vent Exhaust Monitoring System - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
2 PT 7.2.3a - Core Spray Unit Cooler Operability -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
10 PT 1.6.1 - Rod Sequence Control System Operability - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
10 PT 1.6.2 - Rod Worth Minimizer System - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
6 PT 1.10 - SRM & IRM Detector Position Rod Block Functional Test - Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
8 PT 2.1.22 - Steamline Area High Temperature -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
9 PT 2.2.1 - Primary Containment Isolation Valves -
Sign-ot'f page to include "PT Exception Form is Attached."
4-19-78 X
5 PT 2.2.la - Instrument System Isolation Valves -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
6 PT 1.5.4 - For APRM INOP & UPSCALE (12%) -
Sign-off page to include "PT E:.ception Form is Attached."
4-19-78 X
8 PT 1.2.3 - Average Power Re. age Monitor (15%) -
Sign-off page to include "PT Exception Form is Attached."
4-19-78 X
1 PT 12.2d - No. 4 D/G Monthly Load Test - Sign-off page to include "PT Exception Form is Attached."
4-21-78 X
6 PT 8.2.2 - LPCI/RHR - Revised to add ISI requirements.
4-21-78 VI 4
EI 27.3 - Abnormal Release of Radioactivity-Airborne - Corrections and to improve Isopleth Method.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-21-78 XVI 1
A 3,1 RHR System II Actuate 6 - Additions to "Possible Plant Effects" - #3 contamination problems of drywell & radiation problems and #4 possible fuel meltdown.
4-21-78 XVI 1
A 3, 3 Depress VLV Bellows Leaking - Revised to conform to Standard Technical Specifications and addition of ADS valve location and setpoints.
4-21-78 XVI 1
A 3, 2 Core Spray System II Actuated -
Additions to "Possible Plant Effects" - #2 high contamination / radiation problems in the drywell, #3 reactor quality problems, and #4 possible fuel meltdown.
4-21-78 XVI 1
A 3, 3 RHR Sw Pump Ell-C001D Trip - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3 List of Effective Procedures - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 2
A 3 List of Effective Procedures - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3,1 RCIC Logie Bus B Power Failure -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 1 RCIC Turbine CPLG End Brg. Temp. Hi.-
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 1 RHR HX A/B Inlet Wtr. Temp. Hi. -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 2 RCIC Turb. Exh. Press. Hi. - Revised to conform to Standard Tec. 'ical Specifications.
4-21-78 XVI 1
A 3, 1 Core Spray System II Logic Power Failure - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 2 RCIC Turb*ne Exh. Diaph. Press. Hi. -
Revised to conform te Standard Technical Specifications.
4-21-78 XVI 1
A 3, 2 RCIC Turbine Gov. End Brg. Temp. H1. -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 2 RHR Relay Logic B Power Failure -
Revised to conform to Standard Technical Specifications.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-21-78 XVI 1
A 3, 2 RHR SW Pump E11-C001B Overload -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 2 RHR RX A/B Outlet Hi Conductivity -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 3 RCIC Turbine Steam Line Water Dr. Pot Hi. Level - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 3 Core Spray B Hi Press. Valve Leak -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 3 RHR Pump E11-C002B Trip - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 4 RCIC Pump Suction Low Pressure -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 4 RCIC Pump Suction Pressure Hi. -
Revised to conform to Standard Technical Specifications.
4-21-7E XVI 1
A 3, 4 RCIC Barom Cond. Vac. Tank Level Hi. -
Revised to conform to Standard Technical Specifications.
4-21-7E XVI 2
A 3, 4 Core Spray B Hdr. to Core Plt. Top Hi Dp - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 4 RHR Pump E11-C002B Overload - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 4 RHR SW Pump E11-C002D Overload -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 5 RCIC Turbine Tripped - Revised to conform to Standard Technical Specifications.
4-21-7E XVI 1
A 3, 5 RCIC Turbine Oil Pressure Low -
Revised to conform to Standard Technical Specifications.
4-21-7E XVI 1
A 3, 5 Core Spray Pump 2B Tripped - Revised to conform to Standard Technical Specifications.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-21-78 XVI 1
A 3, 5 RHR Pump E11-C002D Trip - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 5 RHR SW Pump "B" Hx-Low Flow High Temperature Stator Water - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 6 RCIC Isol. Trip Signal B Initiated -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 6 RCIC Vacuum Tank Pressure Hi. -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 6 RHR Pump E11-C002D Overload - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 6 Core Spray Pump 2B Overload - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 6 RHR SW Pump "D" Hx-Low Flow High Temperature Stator - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 7, 6 Rx Recire. Drive Mtr. B Overload Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 7, 4 Recire. Loop B Only Out of Service -
Revised to conform
- .o Standard Technical Specifications.
4-21-78 XVI 1
A 7 List of E*.fective Procedures - Revised to conform to S.andard Technical Specifications.
4-21-78 XVI 1
A 7, 4 Outer Seal Leakage Flow Detector B High - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 6 Steam Leak Det A Teep. Hi. - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2 List of Effective Procedures - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 2
A 2 List of Effective Procedures - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 1 Core Spray System II Valve Mtr.
Overload - Revised to conform to Standard Technical Specifications.
1
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 4-21-78 XVI 1
A 2, 1 RHR CR-Tie Valve Ell-F010 Open -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 2-5-RCIC Of1 Filter AP High - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 2-6 '- RCIC System Pressure Low - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 3 RHR Pump A Seal Cool Flow Low -
Reviced to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 3 RCIC Valves Mtr. Overload - Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 3 RHR Pump B Seal Cool Flow Low -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 5 Steam Leak Det. ABM Temperature Hi. -
Revised to conform to Standard Technical Specifications.
4.-21-78 XVI 1
A 2, 4 RHR Pump C Seal Cool Flow Low -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 2, 5 RPV Flange Seal Leak - Revised to conform to Standard Technical Specifications.
4-21-73 XVI 1
A 2, 4~9 - RHR Pump D Seal Cool Flow Low -
Revised to conform to Standard Technical Specifications.
4-21-78 XVI 1
A 3, 5 RCIC Isolation Trip Signal A Initiated - Revised to conform to Standard Technical Specifications.
4-21-78 N/A 0
Special Test 78 HPCI Operational Hydro -
371tial issue.
4-26-78 IV GT 1 - Rod Sequence Checkoff Sheet - Correct I
discrepancies between existing Appendix 1B1 and GE Cycle Management Report.
I e
4-26-78 IX 3
FR 15 - Loading and Unloading the IF-300 Spent Fuel Cask with BWR Fuel - Assigned location for each fuel assembly of loads 3, 5, & 6 changed.
4-26-78 X
5 PT 8.1.4 - RHR 3ersice Water System Component Test - Data shec* was left out during review and typing of rev. 4.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 5-3-78 XII 2
MP 4 - General Maintenance Procedure - The procedure was changed to reflect the requirements of an operating plant; i.e., the sections about startup were removed.
5-3-78 X
2 PT 45.2.10 - Reactor Low Water Level No. 2 Response Time - Initial conditions were left out of Revision 1.
5-3-78 X
7 PT 2.6.5P - Personnel Airlock Interior and Exterior Door - All changes incorporated to cover' Leak Rate testing on both the interior and exterior doors of the Personnel Airlock and to remove the blank flange test from the PT.
5-3-78 XII 1
MT 14 - Corrective Maintenance - To clarify supporting documentation of Q-List trouble tickets to Quality Assurance for final review.
5-3-78 X
2 PT 1.1.7PC - Average Power Range Monitor -
Fixed and Flow Biased (Thermal) Neutron Trips Channel Calibration - Editorial change.
5-3-78 X
0 PT 35.4.5 - Fire Detection System Service Water Building Water Treatment Building Cantrol Building - Initia] issue.
5-3-78 II 1
SD 46 - Instrument and Service Air System -
General revision and update.
5-3-78 X
4 PT 4.1.10 - Service Water Effluent Radiation Monitoring System - Delete the "P" designation and change the comments page to standard operations format.
5-3-78 III 6
OP 52 - 120 Volt A. C. Electrical System -
' ~
Editorial change.
5-3-78 III 15 OP 19 - High Pressure Coolant Injection System -
Add the following sentences to the end of step 3 -
" Press the remote turbine trip pushbutton and ensure the V-8 valve closta fully. Release the pushbutton."
5-3-78 X
7 PT 10.1.3 - Flow Rate at 150 psig - Editorial changes.
5-3-78 X
7 PT 4.1.7 - Off-Gas Radiation Monitoring System Channel Functional Test - Delete the "P" designation and change comments page to standard operations format.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 5-3-78 X
11 PT 4.1.3 - Radwaste Ef fluent Radiation Monitoring System - Delete the "P" designation and change the comments page to standard operations format.
5-3-78 X
N/A PT 8.2.3 - LPCI Motor Operated Valve Operability-Deleted.
5-3-78 X
12 PT 4.1.2 - Main Stack Radiation Monitoring System Channel Functional Test - Delete the "P" designation and change the comments page to standard operations format.
5-3-78 X
N/A PT 8.2.1 - Pump Flow Rate - Deleted.
5-3-78 III 13 OP 24 - Containment Atmospheric Control System -
Revised to conform to new procedure for inerting Drywell without thermal damage to inerting piping.
5-3-78 X
7 PT 4.1.8 - Off-Gas Hi Rad Operability Check -
Addition of caution "If A0G System is inoperable, the plant must be in a shut down condition prior to performing this PT."
5-3-78 XVI 1
A 6, 2 APRM Upscale - Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 3 APRM UPSC Trip /Inop. System A -
Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 5 Outer Seal Leakage Flow Detector A High - Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 4 Recire. "A" Only Out of Service -
Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 4 RBM UPSC/Inop. - Revised to conform to Standard Technical Specifications.
5-3-78 XVI O
A 6, 4 Generator A Internal Air Temperature High - Initial issue.
5-3-78 XVI 1
A 6, 3 APRM UPSC Trip /Inop. System B -
Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 2 Reactor Vessel Lo Water Level System B - Revised to conform to Standard Technical Specifications.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 5-3-78 XVI 1
A 6, 1 LPRM Dohnscale - Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6-List of Effective Procedures - Revised to conform to Standard Technical Specifications.
5-3-78 XVI O
A 6 - List of Effective Procedures - Initial issue.
5-3-78 XVI 1
A 6, 1 LPRM Upscale - Revised to conform to Standard Technical Specifications.
5-3-78 XVI 1
A 6, 1 Reactor Vessel Lo Water Level System A - Revised to conform to Standard Technical Specifications.
5-9-78 X
0 PT 22.0 - Reactor Building Closed Cooling System - Original issue - ISI procedure.
5-9-78 X
0 PT 24.2 - Containment Atmosphere Monitoring System Component Test - Original issue - ISI procedure.
5-9-78 X
0 PT 25.'O - Nuclear Steam Supply - Original issue -
ISI procedure.
5-9-78 X
0 PT 14.6 - Reactor Water Cleanup - Original issue - ISI procedure.
5-9-78 X
0 PT 13.0 - Fuel Pool Cooling and Filtering System Component Test - Original issue -
ISI procedure.
5-9-78 X
0 PT 46.0 - Cold Shutdown Valve Operability Test -
Original issue - ISI procedure.
5-9-78 X
0 PT 11.3 - Drywell Drains System Component Test -
Original issue - ISI procedure.
5-9-78 X
10 PT 10.2 - RCIC - Revised to incorporate ISI test procedures.
5-9-78 X
11 PT 9.2 - HPCI System Component Test - Original issue - ISI procedure.
5-9-78 III 11 OP 32 - Condensate and Feedwater - Add section M for removing a High Pressure Heater Train
(#'. and #5) from service.
5-12-78 X
3 PT 24.1 - Service Water - Revised to incorporate ISI testing.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 5-12-78 X
7 PT 8.2.2 - LPCI/RHR - Adds ISI baseline data for pumps and valves.
5-12-78 X
0 PT 31.5 - Instrument Air System Component Test ISI Procedure in accordance with Standard Technical Specifications.
5-12-78 N/A 1
SP 77 CRD Friction Testing - Adds additional prerequisites and precautions per CNS letter 78-42.
5-12-78 IX 4
FH 15 - Loading and Unloading the IF-300 Spent Fuel Cask with BWR Fuel - Made editorial revisions.
5-12-78 N/A 1
SP 77 CRD Functional Testing - Adds additional prerequisites and precautiora oer CNS letter 78-42.
5-18-78 VIII 1
RC&T 0006 - Sampling Analysis Schedule for ETS Items - To incorporate changes in the ETS.
5-18-78 XII O
MP 30 - General Welding Procedure - Original issue.
5-24-78 1
STP 1 - Reconfiguration of the IF-300 Cask -
Made changes recommended by CNS and made editorial revisions.
5-24-78 X
1 PT 25.1 - Nuclear Steam. Supply - Adds acceptance criteria.
5-24-78 X
6 PT 8.1.4 - RHR SW System Component Test -
Made editorial revisions.
5-24-78 X
0 PT 16.1.1 - Containment Atmosphere Control System Component Test - Original ISI Procedure to comply with Tech. Specs.
5-24-78 III 6
OP 31 - Makeup Water Treatment - Adds step for air fluffing to improve regenerations.
5-24-78 XVI 2
A 5 - Annunciator Procedures - Revised list of effective pages to comply with Plant Mods.76-143 and 76-138, 5-24-78 III 7
OP 43 - Service Water System - Made editorial revision.
5-24-78 XVI 2
AP A 5 (1-6) - Discharge Volume High Water Level CRD Trip - To comply with Plant Mod.76-143.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 5-24-78 XVI 1
AP A 5 (3-7) - Main Steamline Hi/Hi Rad. Trip -
Revised to comply with Plant Mod.76-138.
5-24-78 XVI 1
AP l-A List of Effective Pages - Revised to reflect Tech. Spec. changes.
5-26-78 III 12 OP 32 - Condensate and Feedwater - Added a new section "N" to procedure, placing a High Pressure Feedwater Heater Train in service.
6-2-78 0
STP 78 Transient Response with Loss of One of Two Circulating Water Pumps - Original issue.
6-8-78 XVI 1
UA 25 - Window 5-8 A0G Room Vent Down-Inop - To add CAC 3216 Trip.
6-B-78 X
4 PT 33.2 - Testing Standby EHC Pump - To provide operators more information on determining when EHC power plant filters need replacing.
Remove confusion on determining filter status.
6-B-78 XIV 1
UA 23 - Window 6 Unit Nos.1 & 2 - Changed to conform to Plant Mod. 75-29.
6-8-78 X
13 PT 4.1.2 - Main Stack Radiation Monitoring System Channel Functional Test - Editorial changes.
6-8-78 III 5
OP 47 - Floor and Equipment Drain System - Add Valve Vil14 OG Drain Tank Pump Discharge to Floor Drain System Shut.
6-8-78 XVI 2
UA 28 - Window 3 Reactor Recirculation Inlet Manf. Cond. High - Procedure was incomplete.
6-8-78 X
3 PT 8.2.2A - RHR Unit Coolers Operability -
Delete, no longer required since ISI PT is being run.
6-8-78 III 9
OP 6 - Radwaste - To provide instructions for heating the concentrated waste tank with auxiliary steam during periods when the normal electric heaters are incomplete.
6-8-78 XVI 1
Unit No. 1 Annunciator A-1 Window 1 HPCI Flow LO.
Correct instrument number and reflect new Technical Specification requirements.
6-8-78 XVI 1
Unit No. 1 Annur.ciator A-1 Window 1 HPCI Suction Pressure HI - To meet Standard Technical Specifications.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-8-78 XVI 1
Unit No.1 A-1 Window 6 RHR Ex A Tube to Shell Pressure LO - To identify as a Unit No. 1 procedure.
6-8-78 XVI 1
Unit No.1 A-1 Window' 6 RHR Head Spray Bellows High Leakage - To identify as a Unit No. 1 procedure.
6-8-78 XVI 1
A 1 - Window 6 Unit No. 1 - RHR SW Pump "C" Ex - Low Flow High Temp. stator water -
To meet Standard Technical Specifications.
6-8-78 I
3 PT 7.2.3A - Core Spray Unit Cooler Operability - Delete - Standard Technical Specifications does not require this test because of ISI PT's being run.
6-8-78 III 10 OP 25 - Unit No. 1 - System Electrical Lineup Sheet OP 25.E - Delete Drain Valve MS-V34 (ON) since valve is not installed in the system.
6-8-78 III 6
OP 33 - Startup from Ambient Conditions -
Changes made to meet requirements of Plant Modification 76-359. Lower LN Temp. to 2
cold box.
6-8-78 XVI 2
UA 23 - Window 5 ISI Vibration Trip Disabled-Revised to conform to Plant Mod.75-291.
6-8-78 XVI 2
UA 23 - List of Effective Procedures - Revised to conform to Plant Mod.75-291.
6-8-78 X
7 PT 6.1 - Standby Liquid Control System Component Test - Editorial changes.
6-8-78 X
12 PT 4.1.3 - Radwaste Effluent Radiation Monitoring System Channel Functional Test -
Editorial changes.
6-8-78 III 14 OP 24 - Containment Atmospheric Control - A note was added for Operator clarification.
6-9-78 0
SP 78 HPCI Overspeed Trip Test - To provide direction for the testing of the HPCI.0verspeed Trip Mechanism.
6-10-7E XII 3
MP 29 - Handling the IF-300 Cask Delete RC&T survey.
Surveys are performed in accordance with RC&T-0009.
6-14-78 II 3
SD 9 Neutron Monitoring System (Startup Range) Downscale Trip Change to Meet Standard Technical Specifications.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 X
0 PT 35.15 - Fire Protection Water Pump Flow Test -
New test to meet NFPA, NML, NRC and Technical Specifications requirements.
6-14-78 X
11 PT 10.2 - RCIC - Add baseline data to pump and valve data sheets. Also editorial changes.
6-14-78 X
7 PT 7.2.3 - Core Spray System - Add baseline data to the PT's.
6-14-78 X
1 PT 25.0 - Nuclear Steam Supply - Revised to include baseline data in PT.
6-14-78 X
1 PT 14.6 - Reactor Water Cleanup - Revised to
~
include baseline data in PT.
6-14-78 X
1 PT 22.0 - Reactor Building Closed Cooling System - To add baseline data.
6-14-78 XVI 1
A 1 - Window 4 RHR SW Pump Ell-C001C Over-load - To meet Standard Technical Specifications and to update.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 6 Core Spray Pump 1A Overload -
To meet standard Technical Specifications and to update.
(Unit No. 1) 6-1 4 - 78 XVI 1
A 1 - Window 6 RHR Pump Ell-C002C - Change to meet Standard Technical Specifications.
(Unit No. 1) 6-1 4-78 XVI 1
A 1 - Window 2 Steam Line Break AP HI - To correct dPS setpoint and to meet Standard Technical Specifications.
(Unit No.1) 6 78 XVI 1
A 1 - Window 4 HPCI Turbine Bearing Oil Pressure LO - To meet Standard Technical Specifications and to update.
(Unit No. 1) 6 78 XVI 1
A 1 - Window 1 HPCI Vacuum Breaker Valve F075/079 No Full Open - Rewritten to update.
(Unit No. 1) 6-14-7E XVI 1
A 1 - Window 2 RHR SW Pump Ell-CO0lA Over-load - To meet Standard Technical Specifications 6-14-78 XVI 1
A 1 - Window 3 Suppression Chamber Level HI/LO - To meet Standard Technical Specifications.
(Unit No.1) 6-14-78 XVI 1
A 1 - Window 4 HPCI Turbine Trip So Ener. -
To meet Standard' Technical Specifications.
OPERATING MJdiUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 XVI 1
A 1 - Window 4 RHR Pump Ell-C002A Overload -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI UA 5 - Window 6 TB Supply Air Heat Trouble Delete Procedure - Alarm was' removed by Plant Mod.75-503 and FECP 9104.
(Unit Nos. 1 & 2) 6-14-78 III 17 OP 2 - Reactor Recirculation System - New paragraph for instrument valving and new note referencing GE SIL #203, October 29, 1976.
(Unit Nos. 1 & 2) 6-14-78 III 9
OP 13 - Fuel Pool Cooling and Cleanup - Changes valve position to open to allow either pump to be started during operation and startup.
6-14-78 XVI 1
A 1 - Window 5 RHR Pump Ell-COO 2C Trip -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 5 HPCI Logic Bus-H Power Failure-Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 5 HPCI Turbine Exhaust Diaphragm Pressure HI - Rewritten for clarity and to meet Standard Technical Specifications.
6-14-78 XVI 1
A 1 - Window 4 HPCI System Pressure Low -
Rewritten for clairty and updated.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 5 HPCI Turbine Exhaust LN Discharge Pressure HI - Rewritten for clairty and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 6 Cond. Storage Tank Water
.evel LO - Change setpoint to meet Standard L
Technical Specifications.
(Unit No. 1) 6-14-78 XVI O
UA 12 - Window 4 Alarm Procedure - New procedure to comply with Plant Mod.76-133.
(Unit Nos. 1 & 2) 6-14-78 XVI 1
A 1 - Window 6 Logic Bus Power Failure -
To meet Standard Technical Specifications.
(Unit No. 1) 6-14-7E XVI 1
A 1 - Window 6 Vacuum Tank Level LO - New setpoint and to meet Standard Technical Specifications.
(Unit No. 1) i
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 XVI 1
A 1 - Window 4 Isol. Trip Sig. B - Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 - Window 6 HPCI Turbine IN STM LN DR LVL HI - To identify as a Unit No.1 procedure.
(Unit No. 1) 6-14-78 X
0 PT 35.4.6 - Fire Detection Caswell Beach, Service Building, etc. - New PT to meet requirements of NML and Standard Technical Specifications and to optimize work load.
6-14-78 X
12 PT 9.2 - HPCI System Component Test - Add baseline data.
6-14-78 IV 37 GP 1 - Appendix 2-A2 RWM Group 60 - Added Rods 42-35, 10-35, 34-43 and 18-43 to RWM Group 60.
6-14-78 X
1 PT 24.2 - CAC Monitoring System Component Test -
Add baseline data to valve data sheets.
6-14-78 X
1 PT 16.1.1 - CAC System Component Test - Add baseline data.
6-14-78 X
0 PT 5.4PC - Chloride Intrusion Monitors Calibration and Channel Functional Test -
New PT to meet Standard Technical Specifications.
6-14-7E X
9 PT 3.1.2P - CST Low Water Level Channel Functional Test - To add Unit No. 1 level switch instrument numbers.
6-14-7E X
18 PT 1.1.12P - High Steam Line Rad. Channel Functional Test - Editorial changes.
6-14-7E X
2 PT 1.1.13P - High Steam Line Rad. Channel Alignment and Functional Test - Added a note on reportability and changed instrument accuracy at 10 cps from +25% to +24%.
Editorial changes.
6-14-78 X 1
PT 1.1.1PC - Reactor High Pressure Trip Channel Calibration and Functional Test - Changed accuracy requirement of test gaug'e from +1% to
.1%.
6-14-7E X
17 PT 2.1.17P - Steam Line High Channel Functional Test - Editorial change.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 X
2 PT 2.1.17PC - Steam Line High Flow Channel Calibration and Functional Test - Editorial change.
6-14-78 X
10 PT 17.3P - Plant' Batteries - Identified report-able limits and editorial changes.
6-14-78 X
23 PT 3.1.7P - Reactor Low Water Level #2 and #3 Channel Functional Test - Editorial changes.
6-14-78 X
1 PT 1.1.3XC - High Drywell Pressure Channel Calibration and Functional Test - Added reportable limits in " inches of H 0."
2 6-14-78 X
1 PT 1.1.3PC - High Drywell Pressure Channel Calibration and Functional Test - Added reportable limits in " inches of H 0."
2 6-14-78 X
1 PT 11.1.4PC - High Drywell Pressure Calibration and Functional Test - Added reportable limits in " inches of H 0."
2 6-14-78 X
0 PT 55.5PC - Hydrogen Monitoring Channel Calibration and Functional Test - New calibration PT.
6-14-78 X
0 PT 55.6PC - Recombiner Feed Gas Outlet Temperature Switch Calibration - New calibration PT.
6-14-78 X
0 PT 1.1.2PC - Discharge Volume High Water Level Channel Calibration and Functional Test - New calibration PT required by Standard Technical Specifications.
6-14-78 X
0 PT 1.5.3PC - Source Range Monitor System Channel Calibration - New PT required by Standard Technical Specifications.
6-14-78 XII 3
MP 6 - Operation of Cranes - To comply with OSHA 1910.184 and to satisfy NRC concern.
6-14-78 X
7 PT 8.1.4 - RHR Service Water System Component Test - To comply with LER and prevent violation of Technical Specifications.
(Unit Nos. 1 & 2) 6-14-78 XVI 1
A 7 - Window 5 Scram Plt. Air Hdr. Hi/Lo Pressure - To comply with Plant Mod.76-346 (70 psig to 68 psig).
(Unit No. 1)
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 III 5
OP 46 - Instrument and Service Air Systems to Minimize Air Leakage into Drywell - (Units 1 & 2).
6-14-78 VI 5
El 27.3 - Abnormal Release of Radioactivity -
Airborne - To assist operators in calling up weather.
6-14-78 XVI 1
A 7 Window 5 Scram Plt. Air Hdr. Hi/Lo Pressure - To comply with Plant Mod.76-346.
6-14-78 XVI O
Spare - To identify as Unit No. 1.
6-14-78 XVI
'l A 1 Window 4 RHR Loop B System Pressure LO -
Procedure updated and rewritten for clarity.
6-14-78 XVI 1
A 1 - HPCI Vacuum Tank Level HI - Rewritten for clarity.
(Unit No. 1) 6-14-78 XVI 1
A 1 Windou 5 HPCI Valves Motor Overload -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-7E XVI 1
A 1 Window 5 Core Spray Pump 2A Tripped -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-7E XVI 1
A 1 Window 5 Spare - To identify as Unit No.1 spare.
(Unit No. 1) 6-14-7E IVI 1
A 1 Window 5 RHR "A" Valves Overload -
Rewritten for clarity and to meet Standard Techni-cal Specifications.
(Unit No. 1) 6-14-7E XVI 1
A 1 Window 2 Core Spray System 1 Valves Over-loaded - Rewritten for clarity and to meet Standard Technical Specifications.
6-14-7E XVI 1
A 1 Window 6 HPCI Turbine Exhaust LN Pot.
Level HI - To meet Standard Technical Specifica-tions.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 2 Inverted Power Failure - Rewrit-ten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 2 Core Spray System 1 Actuated -
Rewritten for clarity.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 2 RER Relay Logic Power Failure -
Rewritten for clarity and to meet Standard Tech-nical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 2 Core Spray Loop A System Pressure Low - Rewritten for clarity.
(Unit No.1)
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 XVI 1
A 1 Window 4 HPCI VAC Tank Pressure HI -
Rewritten for clarity and updated.
6-14-78 XVI 1
A 1 Window 3 RHR SW Pump Ell-C001C Trip -
To update and to meet Standard Technical Specifi-cations.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 RHR Loop "A" System Pressure Low - Rewritten for clarity.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 Suppression Chamber Level HI HI -
Addition of instrument numbers and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 Core Spray System I Logic Failure - To meet Standard Technical Specifica-tions.
(Unit No.1) 6-14-75 XVI 1
A 1 Window 1 Core Spray In Test Status -
Addition of panel numbers and rewritten for clarity.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 RHR SW Pump Ell-C001A Trip -
To meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 RHR System I Activated -
Editorial changes and rewritten for clarity.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 Core Spray Loop B System Pressure Low - Rewritten for clarity.
(Unit No.1) 6-14-7D XVI 1
A 1 Window 2 HPCI Oil Filter AP HI - To meet Standard Technical Specifications and addition of repair step.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 2 HPCI Pump Suction LO - Rewritten for clarity and to meet Standard Technical Speci-fications.
Changed alarm setpoint.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 Turbine Trip - To update and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 HPCI Turbine Oil Cooler Out Temperature HI - To meet Standard Technical Specifications.
(Unit No. 1) 6-14-7E XVI 1
A 1 - HPCI Auxiliary 011 Pump Motor Trips on Overload - Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1)
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-14-78 XVI 1
A 1 Window 3 HPCI Isol. Trip Signal B Initiated - Rewritten for clarity, alarm setpoints corrected and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 Core Spray "A" High Pressure Valve Leak - Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No.1) 6-14-78 XVI 1
A 1 Window 3 RHR Pump Ell-C002A Trip-Re-written for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 Oil Tank Level High/ Low -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 N/A 7
SP 76 Reactor Leak Check (Operational Hydro) -
To meet Standard Technical Specifications.
6-14-78 X
1 PT 3.1.6PC - ECCS High Drywell Pressure Channel Calibration and Functional Test - To allow for recording trip / reset values for two switches which operate off a common actuator._ Added reportable limit in " inches of H 0."
2 6-14-78 XII 1
MP 20 - Removal and Installation of Non-Segregated Links - Delete - Procedure now covered in !!I 10.25 6-14-7E X
11 PT 2.1.3P - HPCI Steam Leak Detection System -
Additions made to improve technicians comfort and safety.
6-1 3 - 78 X
0 PT 1.1.12PC - High Steam Line Radiation Channel Calibration and Functional Test - This is a new calibration required by Standard Technical Specifications.
6-20a78 X
1 PT 14.4 - Control Rod Drive Housing Support Inspection - To change tolerance of 1-inch fp.1 to measurement of 0.9 to 1.3 inches.
6-21278 VI 10 EI 1.1 - Primary System Rupture Inside Drywell (leaks) - To simplify procedure.
6-21278 VI 5
EI 1.2 - Rupture Inside Drywell - To incorporate modifications and relocate steps.
6-21-7 E VI 2
El 2 - Loss of Control Rod Shutdown Capability -
To relocate actions and to simplify procedure.
6-21-7E VI 2
EI 3.1 - Control Rod Drop - Relocate / eliminate actions to simplify procedure.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER 6 TITLE / CHANGE 6-14-78 XVI 1 A 1 Window 3 HPCI Isol. Trip Signal B Initiated - Rewritten for clarity, alarm setpoints corrected and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 Core Spray "A" High Pressure Valve Leak - Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 3 RHR Pump E11-C002A Trip-Re-written for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 XVI 1
A 1 Window 1 011 Tank Level High/ Low -
Rewritten for clarity and to meet Standard Technical Specifications.
(Unit No. 1) 6-14-78 N/A 7
SP 76 Reactor Leak Check (Operational Hydro) -
To meet Standard Technical Specifications.
6-14-78 X
1 PT 3.1.6PC - ECCS High Drywell Pressure Channel Calibration and Functional Test - To allow for recording trip / reset values for two switches which operate off a common actuator. Added reportable limit in " inches of H 0."
2 6'-14-78 XII 1
MP 20 - Removal and Installation of Non-Segregated Links - Delete - Procedure now covered in MI 10-25 6-14-70 Y.
11 PT 2.1.3P - HPCI Steam Leak Detection System -
Additions made to improve technicians comfort and safety.
6 - 1 3 - 78 x
0 PT 1.1.12PC - High Steam Line Radiation Channel Calibration and Functional Test - This is a new calibration required by Standard Technical Specifications.
6-2048 X
1 PT 14.4 - Control Rod Drive Housing Support Inspection - To change tolerance of 1-inch +0.1 to measurement of 0.9 to 1.3 inches.
6-2148 VI 10 EI 1.1 - Primary System Rupture Inside Drywell (leaks) - To simplify procedure.
6-2148 VI 5
EI 1.2 - Rupture Inside Drywell - To incorporate modifications and relocate steps.
6-2148 VI 2
EI 2 - Loss of Control Rod Shutdown Capability -
To relocate actions and to simplify procedure.
6-21-7 f VI 2
El 3.1 - Control Rod Drop - Relocate / eliminate actions to simplify procedure.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CMNGE 6-21-78 VI 3
EI 3.2 - Rod Uncoupled - Remove unnecessary actions and incorporate Standard Technical Specifications.
6-21-78 VI 4
EI 3.3 - Control Rod Drift - Relocate actions and incorporate Standard Technical Specifications 6-21-78 VI 3
EI 3.4 - Inability to Move Control Rods -
Relocated actions and incorporated Standard Technical Specifications.
6-21-78 VI 3
EI 3.5 - RPIS Failure - Deleted unnecessary actions.
6-21-78 VI 5
EI 4.1 - MSIV Closure - To simplify procedure.
6-21-78 VI 2
EI 4.3 - Continuous Rod Withdrawal During Power Range Operation - Relocated steps to simplify procedure.
6-21-78 VI 3
EI 4.4 - Continuous Rod Withdrawal During Reactor Startup - Relocated actions to simplify procedure.
6-21-78 VI 5
EI 4.5 - Recirculation Flow Control Failure -
Decreasing Flow - To simplify procedure and incorporate Standard Technical Specifications.
6-21-78 VI 2
EI 4.6 - Recirculation Flow Control Failure -
Increasing Flow - To simplify procedure.
6-21-78 IV 36 GP 1 - General Operating Procedure - Revised Appendixes 1-Al and 2-A2 and incorporated three (3) temporary revisions of 6-10-78, 6-11-78, and 6-14-78.
6-23-78 VIII O
RC&T 0101 - Calibration and Setpoint Determination for Main Steam Line Monitors -
New procedure.
OPERATING MANUAL PROCEDURE CHANGES
'4 REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-7-78 VIII 1
RC&T Procedure 0101 - Calibration and Setpoint Determination for Main Steamline Monitors -
Clarification and editorial revisions, 7-7-78 XIII 8
Emergency Plan - Revised telephone numbers and made other editorial changes.
7-7-78 X
3 PT 1.1.7PC - APRM Fixed and Flow Biased Neutron Trips - Divided into two pts to allow easier performance.
7-7-78
.IVII 7
SI 10 - Vehicular Traffic and Parking Control -
Revised method of designation of construction vehicles.
7-7-78 X
0 PT 35.18 - Roll Up Fire Doors - Original issue.
7-7-78 X
16 PT 3.1.6P - ECCS High Drywell Pressure Channel Functional Test - Made editorial revisions.
7-7-78 X
10 PT 2.1.9P - RCIC Steam Leak Detection System -
Made editorial revisions.
7-7-78 X
3 PT 2.1.9PC - RCIC Steam Leak Detection Channel Calibration and Functional Test - Made editorial revisions.
7-7-78 X
2 PT 3.1.12PC - CS Pump Discharge Pressure ITLIC Channel Calibration and Functional Test - Adds jumper to procedure to place the logic in a tripped condition during this test.
7-7-78 X
8 PT 3.1.lP - LPCI Pump Discharge Pressure Inter-lock Channel Functional Test - Adds jumper to place logic in a tripped condition.
7-7-78 X
7 PT 1.2.2 - Intermediate Range Monitor - Includes PT exception form data.
7-7-78 X
1 PT 16.2 - Primary Containment Volumetric Average Temperature - Adds exception form.
7-7-78 X
1 PT 1.1.4XC - Reactor Low Water Level No. 1 Channel Calibration and Functional Test - Adds jumpers to prevent Turbine or RFP Turbine Trip in Hi Water Level during this test.
7-7-78 X
8 PT 3.1.12P - Core Spray Pump Discharge Pressure Interlock Channel Functional Test - Adds jumper to place logic in tripped condition.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-7-78 X
14 PT 3.1.5P - Reactor Vessel Shroud Level Channel Functional Test - Adds steps to prevent Turbine Trip during test.
7-7-78 X
1 PT 3.1.lPC - LPCI Pump Discharge Pressure Inter-lock Channel and Functional Test - Added jumper to place logic in tripped condition.
7-7-78 X
1 PT 17.8 - Fire Pump Diesel Starting Batteries -
Changed temperature correction factor to conform to vendor manual.
7-7-78 X
3 PT 1.1.8PC - APRM Rod Blocks Channel Calibration -
Revised for clarification.
7-7-78 X
2 PT 1.1.4X - Reactor Low Water Level #1 Channel Functional Test - Added Standard Technical Specification Reference.
7-7-78 X
0 PT 1.1.9PC - APRM Flow Units - Original issue (previously part of PT 1.1.7PC).
7-7-78 X
2 PT 2.1.3PC - HPCI Steam Leak Det. Calibration and Ch'annel Functional Test - Made editorial revisions.
7-7-78 X
3 PT 44.1 - Flood Status - Made editorial revisions 7-7-78
~X 1
PT 1.1.4PC - Reactor Lou Water Level No. 1 Channel Calibration and Functional Test (Units 1 and 2) - Add jumpers to prevent Turbine Trip during this test.
7-7-78 X
1 PT 1.1.4PC - Reactor Low Water Level No. 1 Channel Calibration and Functional Test (Unit 1 only) - Add jumpers to prevent Turbine Trip during this test.
7-7-78 III 16 OP 19 - HPCI - Rewrite of procedure for clarity.
7-7-78 XII 2
MP 19 - Removal and Installation of the Isophase Disconnects Links - Delete, replaced by MI 10-2P.
7-7-78 XVI 1
2-UAl - List of Effective Pages - To update list of effective pages.
7-7-78 XVI 1
2-UA1 (3-8) SU Intake Structure Sump Level Hi-Hi - complete rewrite.
7-7-78 XVI 1
2-UAl (3-9) Intake Canal Level - High - Adds new Technical Specifications Reference.
7-7-78 XIX 0
FP 9 - Pre-Fire Plan - Original issue.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-14-78 X
3 PT 1.1.4X - Reactor Low Water Level No. 1 Channel Functional Test - Adds steps to jumper out RFPT trip during PT.
7-14-78 X
26 PT 1.1.4P - Reactor Lett Water Level No. 1 Channel Functional Test - Adds steps to jumper out RFFT trip during PT.
7-14-78 3
PT 25.2P - Seismic Monitor System - Made editori-al changes.
7-14-78 X
1 PT 1.~1.12PC - High Steamline Radiation Channel and Functional Test - Adds new background dara.
7-14-78 XII O
MP 31 - Electrical Cable and Conduit Installa-tion, Identification and Testing - Original issue 7-14-78 XX 1
EUP 5 - Cable Pull Slip Form Documentation -
Revised for clarity.
7-14-78 II 2
SD 21 - Reactor Building Closed Cooling Water System - To incorporate setpoint changes for FM 78-120 and 78-121 and add information from Unit No. 1 Startup Test.
7-14-78 X
14 PT 17.lP - Plant Batteries - Made editorial revisions.
7-14-78 X
11 PT 17.2P - Plant Batteries - Made editorial revisions.
7-14-78 X
0 PT 1.3.2PC - Turbine Stop and Control Valve Channel Calibration - Original issue to meet Standard Technical Specifications.
7-14-78 X
0 PT 2.1.8PC - RCIC Turbine Exhaust Diaphragm Hi Pressure Channel Calibration and Functional Test - Original issue to meet Standard Technical Specifications.
7-14-73 X
3 PT 3.1 - Reactor Vessel Shroud Level Channel Calibration - Adds steps to jumper and RFPT trip circuit during PT.
7-21-78 X
12 PT 1.5.2P - EMI Rod Blocks - Add channel designa-tions B, D, F, H.
7-21-78 X
2 PT 55.3PC - Reactor Vessel Level Loop Calibra-tion - Revised in accordance with a recent Plant Hodification.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
IRRBER & TITLE / CHANGE 7-21-78 X
0-PT 1.3.lPC - MSIV RPS Position Switch Calibra-tion - Original issue to meet Standard Technical Specifications.
7-21-78 X
4 PT 1.1.7PC - APRM - To correct error made in the last revision (Rev. 3).
7-26-78 2
SP 77-7
~ Control Rod Sequence Exchange - Pro-cedure revised to account for use of BWR simula-tor programs in predicting rod patterns and shapes.
7-26-78 XII 2
MP 16 - Writing Corrective Maintenance Instruc-tions - Complete rewrite to bring MP 16 intc conformance with the Operating Manual and Company QA requirements.
7-28-78 IV 0
OG 8 - Guidelines for Preparation of Mechanical Jumper and Abnormal System Operation Procedure -
Original issue.
7-28-78 X
2 PT 22 - RBCCW System - Revises method of verify-ing valve operability.
7-28-78 X
2 PT 24.2 - CAM System Component Test - Revises method of verifying valve operability.
7-28-78 X
6 PT 10.1.1 - RCIC 1000# Flow Rate Test - To con-form to commitment made to'NRC.
7-28-78 X
7 PT 9.5 - HPCI 1000# Flow Rate Test - To conform to commitment made to NRC.
8-2-78 XVIII 2
PN 18 - Special Work Authorization - Adds distri-bution to work group.
8-2-78 XX 5
ENP 3 - Q-List Modification Procedure - To incor-porate OQA Audit Comments and Environmental Impact Statement.
8-2-78 X
4 PT 24.1 - Service Water - Adds additional accept ance criterial and precautions.
8-8-78 XII 6
MP 27 - Handling the IF-300 Cask - To update procedure to incorporate several recent temporary revisions.
8-11-78 X
3 PT 2.1.3PC - HPCI Steam Leak Detection Calibra-tion and Functional Test - Corrected typographi-cal error.
8-11-78 X
1 PT 1.1.9PC - APRM Flow Units - Made editorial revisions.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 8-11-78 X
19-PT 1.1.12P - High Steamline Radiation Channel Functional Test - Made editorial revisions.
8-18-78 X
4 PT 7.1.8 ISI, Core Spray - Revised frequency of test to monthly.
8-18-78 X
12 PT 10.2 ISI, RCIC - Revised frequency of test to monthly.
8-18-78 X
3 PT 10.1.lA ISI, RCIC - Revised frequency of test to monthly.
8-18-78 VIII
'7 RC&T 0005 Radiological Environmental Monitoring Program - Added additional valves.
8-18-78 IV 37 GP 1 - General Operating Procedure - Updated the Control Rod Sequence exchange.
3-18-78 X
1 PT 11.3 - Drywell Drains System Component Test -
Added baseline data on valve stroking.
8-18-78 X
21 PT 30.1 - Sanitary Waste - Delete entire PT.
8-18-78 X
8 PT 4.1.1 - Reactor Building Vent Exhaust Moni-toring - Correct errors and add information.
8-18-78 KVI 0
UA-3 Annunciator Procedures, Unit No. 2 -
Implement FECP 1237.
8-18-78 KVI 2
Annunciator Panel 1A1,~4-10 and 3 RHR Loop
'B' System Pressure Lov and RER Loop 'A' System Pressure Low - Check the valve rather than open the valve.
8-18-78 III 7
OP 31 - Operating Procedure, Makeup Water - Water pressure lowered from 40 to 20 psig.
8-18-78 VI 2
EI 37.1 - Operation During Hurricane Warning and Hurricane Conditions - Include section for Caswell Beach.
8-18-78 IX 3
FH 13 - Fuel Handling Procedure, PWR Fuel Hand-ling Operations - Changed "SR0" to " qualified member of the plant staff as long as an SRO is on the refueling bridge."
8-18-78 X
2 PT 34.1 - Auxiliary Boiler System - Change Acceptance Criteria and add a step to observe lights.
~
8-18-78 III 6
OP 32.2 - Operating Procedure, Condensate Filter Demineralizer System - Add two additional valves.
OPERATING MANUAL PROCEDURE CHANCES I
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 8-18-78 X
12 PT 1.2.4 - APRM High Flux and Downscale Test -
Includes step to turn power pot full CCW.
8-18-78 III 13 OP 17.- Operating Procedure, Residual Heat Removal (RHR) - Close valves prior to pump shutdown.
8-28-78 XII 1
MP 31 - Electrical Cable and Conduit Installa-tion, Identification, and Testing - Revised to address means of adding fire protection to cables and the termination of cables.
8-29-78 X
7 PT 8.1.3 - LPCI/RHR System Component Test -
Revised the procedure per the latest discussions with the NRC.
8-29-78 X
6 PT 8.2.4 - RHR Service Water System Component Test - Revised the procedure per the latest discussions with the NRC.
9-8-78 X
7 PT 10.1.1 - RCIC 1000 PSIG Flow Rate - Corrects procedure to close F008 valve rather than F022 in step 17.
9-8-78 X
4 PT 10.1.la - RCIC System Component Test - Made editorial revisions.
9-8-78 X
3 PT 45.1 - Loading Dock Transfer Lines Hydro -
Made editorial revisions.
9-8-78 X
2 PT 16.2 - Primary Containment Volumetric Average Temperature - Made editorial revisions.
9-8-78 X
4 PT 16.1 - Containment Atmosphere Control System - Made editorial and typographical corrections.
9-8-78 X
3 PT 34.1 - Auxiliary Boiler System - Revised to allow proper operation of Standby Fuel Oil Pumps.
9-8-78 III 6
OP 46 - Instrument and Service Air System -
Revised in accordance with a Plant Modification.
9-8-78 III 1
OP 29 Caswell Beach Operations - To update and revise in accordance with Plant Modifica-tion 77-33.
9-8-78 III 6
OP 29 - Circulating Uater System - Made editorial revisions and revised in accordance with a Plant Modification.
9-8-78 III 5
OP 27 Generator Gas - Revised in accordance with TIL #689.
OPERATING MANUAL PROCEDURE CIWICES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9-8-78 IX 10 FH 9 - New Fuel Receiving and Inspection - Made editorial revisions.
9-12-78 X
0 PT 2.10.3PC - HPCI Isolation Inst. Calibration -
Original issue per Standard Technical Specifica-tions.
9-12-78 X
0 PT 2.1.22PC - Main Steamline Area Temp. Switches Calibration and Channel Functional' Test - Origi-nal issue per Standard Technical Specifications.
9-12-78 X
0 PT 2.1.16PC - RWCU High Flow Channel Calibration and Functional Test - Original issue per Standard Technical Specifications.
9-12-78 X
11 PT 2.1.9P - RCIC Isolation (Steam Leak) Channel Functional Test - Made editorial revisions.
9-12-78 X
22 PT 1.1.7P APRM Neutron & Flow Biased Trips -
Made editorial changes and revised contact point for checking relays.
9-12-78 X
2 PT 1.1.12PC - High Steamline Hi Rad. Channel Calibration and Functional Test - Revised back-ground per latest survey.
9'12-78 X
4 PT 2.1.9PC - RCIC Steam Leak Det. System Channel Calibration and Functional Test - lbde editorial revisions and corrected test voltage.
9-12-78 XII 7
MP 27 - Handling the IF-300 Cask - Adds contact-ing Shift Foreman on all major cask handling evolutions.
9-12-78 X
1 PT 19.6.0.2 - Visual Inspection of Accessible Snubbers on Safety Related Systems - To revise frequency per Technical Specifications and give LCO instructions.
9-12-78 X
1 PT 19.6.0.1 - Visual Inspection of Inaccessible Snubbers on Safety Related Systems - Includes additional instructions, revise frequency per Technical Specifications, and give LCO instruc-tions.
9-12-78 X
10 PT 4.1.6F - Air Sampling System & Waste Gas Effluent Monitors - Added note to specify which scalers are to be stopped prior to testing channels.
9-12-7E X
1 PT 55.2PC - Reactor Pressure Loop Calibration -
Adds jumper to prevent a turbine trip during performance of PT.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9-12-78 X
0 PT 2.10.9PC - RCIC Isolation Instrument Leak Channel Calibration and Functional Test -
Original issue as required by Standardized Technical Specifications.
9-14-78 X
5 PT 7.1.8 - Core Spray System Component Test -
Added baseline data, entire procedure updated.
9-14-78 X
8 PT 8.1.3 - LPCI/RHR System Component Test -
Added baseline data, revised acceptance criteria.
9-14-78 X
12 PT 9.2 - HPCI System Component Test - Divided Technical Specifications and ISI pump testing.
9-14-78 X
4 PT 9.3A - HPCI System Component Test - Divided Technical Specifications and ISI pump testing.
9-14-78 X
8 PT S.I.4 - RER SW System Component Test -
Divided Technical Specifications and ISI pump testing.
9-14-78 X
7 PT 8.2.4 - RHR SW System Component Test -
Divided Technical Specifications and ISI pump testing.
9-14-78 X
8 PT 8.2.2 - LPCI/RHR - Separated monthly ISI &
quarterly Technical Specifications requirements.
9-14-78 X
8 PT 7.2.3 - CS System - Separated monthly ISI &
quarterly Technical Specifications requirements.
9-14-78 X
0 PT 1.13 - LPRM Vibration Monitoring - Original issue, added Unit No. 1 LPRM monthly vibration monitoring procedure.
9-15-78 XIX 1
FP 8 - Fire Barrier Penetration Seal-Work, Permit Control - To incorporate commitment made to NRC and update permits forms.
9-19-78 VIII 2
RC&T 0101 - Calibration & Setpoint Determination for Main Steamline Monitors - Revised this method of calibration to allow more flexibility.
9-22-78 X
4 PT 19.6.1 - Safety Related Junpers - Functional Testing - Correct Technical Specifications reference and provide for testing of Grinnell snubbers.
9-22-78 X
2 PT 19.6.0.1 - Visual Inspection of Snubbers on Safety Related Systems - Revised acceptance criteria.
OPERATING MANUAL PROCEDURE CHANGES i
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9-22-78 X
8-PT 4.1.7 - Off-Gas Radiation Monitoring System Channel Functional Test - Add tolerances from SD and action to be taken if monitor is found out of specifications.
9-22-78 III 15 OP 17 - Residual Heat Removal System - Revised procedure for securing from shutdown cooling mode.
9-22-78 XX 0
ENP 8 - Specification Preparation - Original issue.
9-22-78 IX 11 FH 9 - New Fuel Receiving and Inspection -
Updated procedure to allow for receipt and storage of Unit No. 1 reload.
9-28-78 X
1 PT 1.1.2PC - Discharge Volume High Water Level Channel & Functional Test - Corrects typographi-cal in acceptance criteria - Changed "104 + 5 Gallons" to "105 + 4 Gallons."
9-28-78 X
14 PT 2.1.5P - RCIC Turbine Steamline Low Pressure Channel Functional Test - Deletes unnecessary steps in the refuel mode.
gg 9-28-78 X
18 PT 1.3.lP - MSIV Closure Channel Functional Test - Add jumper under equipment list.
9-28-78 X
3 PT 55.3PC - Reactor Vessel Level Loop Calibra-tion - Adds steps to jumper out turbine trip during performance of PT.
9-28-78 X
1 PT 2.1.5PC - RCIC Turbine Steamline Low Pressure Calibration & Functional Test - Deletes Unnec-essary steps in the refuel mode.
9-28-78 X
4 PT 1.1.4X - Reactor Low Water Level #1 Channel Functional Test - Made editorial revisions.
OPERATING MANUAL PROCEDURE CHANGES i
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 10-4-78 X
38 GP 1 - General Operating Procedure - Revised Control Rod Sequence 1-A2 per GE Cycle Manage-ment Report.
10-4-78 X
1 PT 19.6.2 - Inspection of BOP Snubbers - Delete -
being investigated for inclusion in Preventative Maintenance Program.
10-4-78 X
5 PT 41.1 - Reactor Building Crane - Deletes check-out of motor heater circuit, 10-4-78 II 2
SD 27 Stator Cooling - Settings changed per GE TIL-873 and FM 78-231 and PM 78-232.
10-9-78 X
1 PT 24.0 - Service Water - To comply with ISI Requirement per ASME Section XI.
10-9-78 X
5 PT 24.1 - Service Water Lube Water - To separate monthly and quarterly testing requirements.
10-9-78 X
0 PT 24.1.1 - Service Water Lube Water - To separate monthly and quarterly testing require-ments.
10-11-78 I
4 PT 35.1 - Fire Protection System - Revised Acceptance Criteria to prevent unnecessary calibration of pressure switches.
10-11-78 X
13 PT 9.2 - HPCI System Component Test - Corrects PT.
10-11-78 X
3 PT 45.2.16 - Reactor Water Cleanup High Flow Response Time - Revised instrument setpoint per Plant Mod.77-399.
10-11-79 X
0 PT 5.4.lPC - Chloride Intrusion Monitor Calibra-tion - Original issue as per Standard Technical Specification.
10-11-78 I 26 Volume I - Administrative Procedures - Refet ances Book 1 TI-104 for training and retraining requirements for auxiliary operators and adde instructions and form for PT exception.
10-11-78 XII 1
MP 30 - General Welding Procedure - To clarify the use of the Weld Data Card.
OPERATING MANUAL PROCEDURE CHANCES q
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 10-11-78 X
1 PT 3.1.22 - Reactor Coolant Recirculation System-Adds baseline data.
10-11-78 X
5 PT 10.1.1.a - RCIC Eystem Component Test - Adds baseline data.
10-11-78 XII 1
MP 21 - Utilizing Services of Furmanite On-Line Leak Repair Service - Delete, as MP 14, Correc-tive Maintenance, and MP 16, Writing Corrective Maintenance Instructions, provide controls for implementing repairs.
10-11-78 VI 7
EI 31 - Reactor Scram - Revised to prevent un-necessary Group I Isolation, reduce CRD seal deterioration and adds azimuth locations for vhrious components.
10-11-7E VI 5
EI 28 - Plant Shutdown from Outside Control Room-Adds azimuth location of relief valves and tours penetrations.
10-11-7E VI 4
EI 4.2-Moderator Temperature Decrease - Delete reference to Unit No. 1 as Unit No. 1 does not have SRI Bus.
10-11-75 VI 6
EI 27.3 - Abnormal Release of Airborne Radioacti-vity - Add instructions for manual acquisition of MET Towers Data, if remainder of system is INOP.
10-ll-7E VI S
EI 40 - Safety / Relief Valve Fails Open - Adds azimuth location for relief valves.
10-ll-7E IV 39 GP 1 - General Operation Procedure - Adds steps for Automatic Load D'spatch Mode.
i 10-11-7E III 4
OP 38 - Fuel Oil System - Adds precaution to ensure tank truck / rail car is grounded prior to starting pump.
10-11-7E III 12 OP 10 - Standby Gas Treatment System - Revised setpoints per Plant Mod. 77-27.
10-ll-7E III 10 OP 6 - Radwaste - Adds valve V120 in the 20 GPM Concentrator Valve Lineur<
10-11-7E III 2
OP ?7 Radwaste HVAC - Adds caution to ensure stack dilution air flow when either unit is operating.
10-ll-7E III 15 OP 24 - Containment Atmospheric Control System -
Made editorial revisions.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 10-ll-7E X
8 PT 9.5 - HPCI 1000 PSIG Flew Ra*e Test - Adda step to verify that turbine stop valve goes shut with the remote turbine trip button on RTGB.
10-11-78 X
7 PT 9.3 - HPCI 165 P3IG Flow Test - Adds step to verify that turbir.e stop valve goes shut with. the remote turbine trip button on RTGB.
10-11-78 X
8 PT 6.1 - Standby Liquid Control System Component Test - Adds precautior on overtorquing flow tape on accumulator.
10-20-78 XX 0
ENP 9 - Procedure for Performing Core Bores through Secondary Containment - Original issue.
10-20-78 0
STP 78 Automatic Load Dispatch - Original issue to verify the Brunswick Unit load following capability. -
10-20-78 X
9 PT 8.1.3 - LPCI/RHR System Component Test - This revision allows isolating the gsuges protecting them from pressure transient.
10-26-78 XII 2
MP 28 - Inutallation of Spent Fuel Baskets - To add step for cleanliness inspection.
10-26-78 I
26 Volume I - Administrative Procedures - References training instructions, clarifies implementing instructions, adds QA review of surveillance tests and adds PT exception form.
11-3-78 0
STP 78 Radwaste Cleanup - Initial israe.
11-9-79 I
27 Volume T. - Administrative Procedures - To update Operations Section, Section 4, and clarify function and updating of the Plant Operating Manual Index.
11-9-78 VIII 5
RC&T 0004 - Instrument Calibration Control - Made editorial changes and changed Main Steam Line and Drywell Atmosphere Calibration frequencies in accordance with Technical Specifications, 11-9-78 XIII 9
Volume XIII - Emergency Plan - changed ERDA to DOE and added new letter of agreement with DOE.
L1-9-78 X
4 PT 2.1.3PC - Stean Leak Detection - Adds note to perform PT 45.2.3 in conjunction with this PT.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 11-9-78 X
2 PT 1.1.4PC - Peactor Low Watar Level No.1 - Adds note to perform PT 45.2.7 in conjunction with this PT.
11-9-78 X
2 PT 1.1.lPC - Reactor High Pressure Trip Channel.-
Adds note to perform PT 45.1.3 in conjunction with this PT.
11-9-78 X
2 PT 45.1.2 - Reactor Low Water Level #1 - Revised to allow performance of this PT during plant operation.
11-9-78 X
2 PT.l.l.9PC - APRM Flow Units - Adds additional checks during calibration.
11-9-78 X
0 PT 19.8.5P - Cathodic Protection System - Recti-fier #5 Inspection-Separates original PT into five separate PT's, one for each rectifier.
11-9-78 X
0 PT 19.8.4P - Cathodic Protection System - Recti-fier #4 Inspection-Separates original PT into five separate PT's, one for each rectifier.
U 78 X
0 PT 19.8.3P - Csthodic Protection System - Recti-fier #3 Inspection-Separates original PT into fivc separate PT's, one for each rectifier.
11-9-78 X
0 PT 19.8.2P - Cathodic Protection System - Recti-fier #2 Insepetion-Separates original PT into five separte PT's, one for each rectifier.
11-9-78 X
0 PT 19.8.lP - Cathodic Protection System - Recti-fier #1 Inspection - Separates PT's, one for each rectifier, 11-16-78 XVI 1
AP A-5(5-5), Unit Eo. 1 - Drywell Low Pressure Alarm - Requires logging of drywell pressure every 15 minutes and start reading manometer in south core spray room.
11-16-78 XVI 1
AP A-5(5-5), Unit No. 2 - Drywell low Pressure Alarm - Requires logging of drywell pressure every 15 minutes and start reading manometer in south core spray room.
11-16-78 III 16 OP 17 - Residual Heat Removal - Adds note #10 which indicates to open manual valve between Reactor Building and torus vacuum breakers prior to operation of the drywell or suppression pool spray systems.
OPERATING MANUAL PROCEDURE CHANCES i
REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 11-16-7E III 16 OP 24 - Containment Atmospheric Control - Adda precautions 7 and 8 concerning recording drywell pressure and not to operate SEGT while adding LN2 for inerting.
11-21-70 X
3 PT 35.5 - Fire Extinguisher Service & Inspection-Deletes recording of serial numbers for specific locations.
11-22-78 II 3
SD 20 - Automatic Blowdown System - Revises safety relief valve setpoint per technical speci-fication revisions.
11-22-78 VI 9
EI 40 - Safety / Relief Valve Fails Open - Revised technical specification reference.
11-22-78 VI 8
EI 31 - Reactor Scram'- Attaches CRD position (computer printout) after scram to procedure.
11-22-78 III 21 OP 14 - Reactor Water Cleanup - Revised to pre-vent getting resin into the reactor vessel.
11-22-78 X
8 PT 8.2.4 - RHR Service Water System - To incor-porate baseline data.
11-22-78 III 18 OP 2 - Reactor Recirculation System - Adds cau-tion and revises valve lineup per Plant Mod.
77-53.
11-29-78 IV 40 GP 1 - General Operating Procedure - Added step for cracking.open RFP suction valve to prevent having to open the valve with high AP.
11-29-78 X
8 PT 9.3 - HPCI 165 psig Flow Test - To conform to present technical specifications.
11-29-78 IX 5
FH 15 - Loading and Unloading the IF-300 spent Fuel' Cask with BWR Fuel - Allows locetion and orientation by persons other than the QA or bridge operation.
11-29-78 IX 4
FH 13 - PWR Fuel Handling Operations - Allows location and orientation by persons other than the QA or bridge operation.
ll-29-78IVIII 1
PN 16 - Plant / Equipment Key Checkout - Modified controlled key control.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 11-30-7E Vol. I 28 Volume I - Administ'rative Procedures - Updated per latest Organization change.
ll-30-7E XVII 17 SI 9 - Access Control and Personnel Identifica-tion - To allow access to Reactor Building for badged NRC personnel without completing Form 9.8.
12-6-78 X
8 PT 4.1.1 - Process Rad. Monitors - Adds Step 16.
12-6-78 III 6
OP 26 EHC Hydraulic System - Made revisions
'trd additions in steps for adding EHC Fluid.
12-6-78 X
1 PT 31.5 - Instrument Air System Component Test -
Corrects valve lineup sheets.
12-6-78 III 10 OP 50 Diesel Gen. Emergency Power System -
Revised in accordance with plant modification 76-93 (FECP 1250A).
12-6-78 III 8
OP Make up Water Treatment - Provide in-structions for air mix and backwash of carbon filters.
Reference PM 76-236,76-345, and 76-406.
12-6-78 III 6
OP 44 - Turbine Building Closed Cooling System -
Revised in accordance with PM 77-247.
12-6-78 X
3 PT 24.2 - CAC System Component Test - Deletes test of Power Failure for valves which fail as is in loss of power.
12-6-78 X
9 PT 1.5.1 - Rod Block Monitor - Made corrections for differences between units and clarified fre-quency requirements.
12-6-78 IV 4
OG 2 - Technical Specification LCO Followup -
Made additional revisions for initiation of an LCO sheet.
12-6-78 X
8 PT 10.1.1 - RCIC 1000 psi Flow Test - Changed valve to be adjusted for proper flow and pressure to a throttle valve.
12-6-78 X
0 PT 27.1 - Hydrogen Seal Oil System - Original issue.
12-6-78 XVI 1
Annunciator Procedure 2UA-19/1-UA-19 (5-3) - Loss of EXC AC Power - Revised in accordance with PM 75-412.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 12-6-78 X
2 PT 45.1.4 - APRM Neutron Flux High (15% & 120%)
Response Time - Allows performing this PT in Run Mode.
12-6-78 X
2 PT 45.1.3 - Rx. Hi Pressure Trip Response Time -
Allows performing this PT in Run Mode and adds note to perform this PT in conjunction with PT 1.1.lPC.
12-6-78 X
2 PT 45.2.11 - Main Steamline Low Pressure Response Time - To allow performing this PT in run.
12-6-78 X
1 PT 2.3.4 - Suppression Pool - Rx. Bldg. Vacuum Breakers - Made editorial changes and revised to allow performing this PT while operating.
12-6-78 X
1 PT 2.1.22PC - Main Steamline Area Temp. SW. Cali-bration and Channel Functional Test - Adds note to perform this PT in conjunction with PT 45.2.1.
12-6-78 X
0 PT 19.8.6P - Cathodic Protection System - Sewage Treatment Plant Inspection - Separated original into separate PT for each rectifier.
12-6-78 X
0 PT 56.4PC - Reactor Vesse.1 Level Loop Calibra-tion - New Calibration PT as required by Stan-dard Technical Specifications.
12-6-78 X
0 PT 56.5PC - Post Accident Reactor Pressure in-strumentation Loop Calibration - New Calibration PT as required by Standard Technical Specifica-tions.
12-6-78 X
0 PT 20.lPC - Intake Canal Level Instrumentation Channel Calibration and Functional Test - New Calibration PT as required by Standard Technical Specifications.
12-6-78 X
0 PT 2.1.15PC - RWCU Spare High Temp. and High Diff.
Temperature Calibration and Functional Test - New Calibration PT as required by Standard Technical Specifications.
12-6-78 X
0 PT 56.2PC - Suppression Chamber Level Loop Cali-bration - New Calibration PT as required by Stan-dard Technical Specifications.
12-6-78 X
2 PT 45.2.12 - Main Steamline High Flow Response Time - Revised to allow PT to be performed with plant operating.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 12-6-78 X
2 PT 45.2.8 - High Drywell Pressure Response Time -
Adds note.to perform this PT in conjunction with PT 1.1.3PC.
12-6-78 X
2 PT 1.1.3PC - High Drywell Pressure Channel Cali-bration and Functional Test - Adds note.to per-form this PT in conjunction with PT 45.2.8.
12-6-78 X
3 PT 45.2.10 - Reactor Low Water Level #2 Response Time - Made editorial changes and adds note to perform this PT in conjunction with PT 2.1.4PC.
12-6-78 X
3 PT 45.2.7 - Reactor Low Water Level #1 Response Time - Made editorial revisions and adds note to perform this PT in conjunction with PT 45.1.2.
12-6-78 X
3 PT 45.2.1 - Mn. Steam Tunnel Temp. Switch Re -
sponse Time - Adds note to perform this PT in conjunction with PT 2.1.22PC.
12-6-78 X
2 PT 45.2.3 - HPCI Stm. Tunnel Temperature - High Response Time - Adds note to perform this PT in conjunction with PT 2.1.3PC.
12-6-78 III 22 OP 14 - Reactor Water Cleanup System - Reflects the discontinuance of Solka-Floc.
12-6-78 X
10 PT 14.1 - Control Rod Operability Check - Obtains data on CRD failures.
12-6-78 X
1 PT 55.lPC - Drywell Pressure Loop Calibration -
Revised in accordance with latest Technical Specifications.
12-6-78 X
1 PT 5.4C - Chloride Instrusion Monitors Calibra-tion and Channel Functional Test - Made editorial revisions and corrected mistakes.
12-6-78 X
1 PT 55.5PC - Hydrogen Monitoring Channel Calibra-tion and Functional Test - Made editorial revi-sions.
12-6-78 X
0 PT 17.llP - Spare Plant Batteries - Original issue.
12-6-78 XVI 1
Annunciator Procedure A-6 (6-6) and (5-6)
- Re-vised in accordance with PM 77-398.
12-6-78 XVI 1
Annunciator Procedure UA-3 (4-4) - Revised in accordance with PM 77-247.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 12-8-78 VI 1
EI 45 - Explosion in Off-Gas Piping - To clarify recovery procedure.
12-13-7E VI 8
EI 27 Abnormal Release of Radioactivity -
Simplified Isopleth calculations and immediate actions.
12-18-7E X
5 PT 1.1.7PC - APRM - Fixed and Flow' Biased Neutron Trips Channel Calibration - Provides for checking "As Found" readings prior to any adjustments and revises method of jumping K12 contacts.
12-18-7 E X
2 PT 1.1.3XC - High Drywell Pressure Channel Cali-bration and Functional Test - Made editorial change concerning resetting Groups 2 and 3.
12-18-7E X
5 PT 3.1.17 - Recire. Pump Trip - Delete - This procedure incorporated into new PT 3.2.
12-18-7E X
3 PT 3.1.20 - Recire. Pump Trip - Delete - This procedure incorporated into new PT 3.2.
12-18-7E X
0 PT 3.2 - Recire. Pump Trip Logic Functional Test-Original issue.
12-18-7E X
2 PT 1.1.3X - High Drywell Pressure Channel Func-tional Test - Made editorial changes concerning resetting Groups 2 and 3.
12-18-7E X
15 PT 1.1.3P - High Drywell Pressure Channel Func-tional Test - Made editorial change concerning resetting Groups 2 and 3.
12-18-7E X
18 PT 2.1.17P - Group I Steamline Hi Flow Channel Functional Test - Made editorial correction.
12-18-71 X
13 PT 1.5.2P - IRM Rod Blocks - Revised to allow performing this PT in RUN mode.
12-18-7f X
12 PT 1.5.3P - SRM Rod Blocks Channel Functional Test - Revised to allow performing this PT in RUN mode.
12-18-7E X
4 PT 1.1.8PC - APRM Rod Block Channel Calibration -
Revised to allow performing this PT in RUN mode.
12-18-7E X
8 PT 1.2.3PC - APRM (15%) Channel Calibration -
Revised to allow performing this PT in RUN mode.
OPERATING MANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE /CliANGE 12-19-7E X
0 PT 60.1 - Six Inch Fuel Pool Cooling Check Valves
- To implement ISI for valves required by Tech-nical Specifications.
12-20-78 X
41 GP 1 - General Operating Procedure - Adds addi-tional rods to Rod Sequence Check Off Sheet for end of cycle operation.
12-27-7E VIII 4
RC&T 0008 - Radioactive Liquid Effluent Releases and Reports - Incorporated second radwaste dis-charge line and made editorial revisions.