ML19296D417
| ML19296D417 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1979 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19296D405 | List: |
| References | |
| B3510, NUDOCS 8003040556 | |
| Download: ML19296D417 (100) | |
Text
.
g UNIT NO.
I SAFETY RELATED PLANT HODIFICATIONS - 1979 O
100.
COMPL.
FSAR TITLE / DESCRIPTION SAFETY ANALYSIS NO.
DATE REV*
NO.
REV.79-054 4520 4-10-79 CRD Return Line Thermal Sleeve Since the CRD return line is blocked a Yes No special test was performed (STP-77-4)
This plant mod removed the CRD which verified system operability in this Return Line Thermal Sleeve from pode.
With no flow in the return line, the Reactor Pressure Vessel.
there is no need for the thermal sleeve.
Removal of the thermal sleeve is With the removal of the thermal sleeve,
- possible, i.e.,
permissible, the safety of the reactor vessel is not since the return line has been affected since no thermal transients at closed. Although the thermal the return line safe end will occur sleeve could remain in the RPV, with no flow in the CRD return line.
it is desirable to remove the thermal sleeve to eliminate the possibility of corrosion
~
occurring and of the nuts and washers coming loose and falling in the vessel.
e 79-098 4820 6-9-79 CAC Containment Isolation Logic A review of the CAC containment It was determined that a single failure Yes No
{y valves' isolation logic revealed in the CAC Isolation Valve override logic that a single failure in the could result in a loss of primary g
c:
isolation override circuitry containment integrity during a LOCA.
l could result in a failure of the This modification removes this logic to CAC isolation valves to isolate assure CAC containment isolation does re during an accident. This occur.
modification removes the isola-tion override from the twelve CAC valves, (V5,V6,V7,V9,V22, V23,V47,V48,V49,V50,V55, & V56) f}
to ensure they close.
01o
i 2
UNIT NO.
SAFETY RELATED PLANT MODIFICATIONS - 1979 H0D.
ColfPL.
FSAR FILE TITLE / DESCRIPTION SAFETY ANALYSIS NO.
DATE REV.
NO.
REV.79-057 4520 7-11-79 CRD Return Line Thermal Sleeve This plant mod removed the CRD Since the CRD return line is blocked, a Yes No Return Line Thermal Sleeve from special test was performed (STP-77-4) the Reactor Pressure Vessel.
which verified system operability in this Removal of the thermal sleeve mode.
With no flow in the return line, is possible, i.e.,
permissible, there is no need for the thermal sleeve.
since the return line has been With the removal of the thermal sleeve, closed. Although the thermal the safety of the reactor vessel is not sleeve could remain in the RPV, affected since no thermal transients at the it is desirable to remove the return line safe end will occur with no thermal sleeve to eliminate flow in the CRD return line.
the possibility of corrosion occurring and of the nuts and washers coming loose and falling in the vessel.
e 79-099 4820 6-9-79 CAC Containment Isolation Logic A review of the CAC containment it is determined that a single failure in Yes No valves' isolation logic revealed the CAC isolation valve override logic that a single failure in the could result,in a loss of primary contain-isolation override circuitry ment integrity during a LOCA.
This could result in a failure of the modification removes this logic to assure CAC isolation valves to isolate CAC containment isolation does occur.
during an accident. This modification removes the isola-tion override from the twelve CAC valves, (VS,V6,V7,V9,v22, V23,V47,V48,V49,V50,V55 & V56) to ensure they close.
9
OPERATING MANUAL PRCCEDURE CHANCES REV.
DATE VOL.
NO.
NUM3ER & TITLE / CHANCE l-4-79 XI 1
QAP 3 - Periodic QA Training - Delete entire pro-cedure. Requirements are being met by the Employee Indoctrination Program and individual group Training Instructions.
1-4-79 XI 2
QAP 1 - Preparation and Control of Quality Assurance Instructions and Procedures - Delete Manager - Quality Assurance Bulk Power Supply approval of QAI's and QAP's and adds attachment No. 2, QAI Revision Form.
1-4-79 XVII 18 SI 9 - Access Control and Personnel Identifica-tion - Reuses Attachment 7, Access Request and Authorization to incorporate additional informa-tion required by new security system.
1 SP 76 Jet Pump Inlet / Mixer P'.ugging - Com-1-4-79 plete revision to improve procedure.
1-10-79 X
8 PT 20.3 - Local Leak Rate Test of Contain=ent Isolation - Overall improvement.
1-10-79 X 3
PT 1.1.12PC - High Steamline Rad. Channel Cal.
and Functional Test - Made editorial revisions.
1-10-79 X 0
PT 2.1.21PC - Low Condenser Vacuum Cal. and Channel Functional Test - Original issue to meet Standardized Tech. Specs.
1-10-79 X 7
PT 11.1.1 - ADS Logic Functional Test - lbde editorial revisions and added step for calibra-tion of ADS timers.
1-10-79 X 3
PT 1.1.3PC - High Drywell Pressure Channel Cali-bration and Functional Test - Made editorial revision.
1-10-79 X 0
PT 1.7.lPC - CRD Accumulator Leak Detection Instrument Calibration and Functional Test.
Original issue to meet Standardized Tech. Specs.
1-10-79 X 0
PT 56.3PC - CAC Torus /Drywell Temp. Mon. Inst.
Calibration and Functional Test - Original issue to meet Standardized Tech. Specs.
1-10-79 X 14 PT 1.5.2P - IRM Rod Blocks - Made editorial revisions.
1-12-79 0
SP 79 In-Core Vibration Sensor and L3rdware Removal - Original issue.
0 SP 79 RPV Internals Inspection - Original 1-12-75 issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CEu'GE l-12-79 IV 42 GP 1 - General Plant Operating Procedure - To ensure Operations personnel are aware of drywell hatch leak testing requirements before Primary Centainment =ay be established.
1-12-79 X
8 PT 1.2.2 - Intermediate Range Monitor - Incorpor-ated into PT 1.5.2P.
(Deleted) 1-12-79 X 7
PT 1.5.4 - Control Rod Blocks (APRM Upscale and Inop) - Makes editorial changes to return system to normal operation.
1-12-79 X
2 PT 12.2a - No. 1 D/G Monthly Load Test PT - Made editorial revisions and incorporated Tech. Rep.
recec=endations.
1-12-79 I 5
FH 11A - Refuel Platform Operations - Adds require =ent to complete inspection of refueling platform prior to placing platform in service.
1-12-79 X
2 PT 12.2b - No. 2 D/G Monthly Load Test - }bde editorial revisions and incorporated Tech. Rep.
recommendations.
1-12-79 X
2 PT 12.2c - No. 3 D/G Monthly Load Test - Made editorial revisions and incorporated Tech. Rep.
recommendations.
1-12-79 X
2 PT 12.2d - No. 4 D/G Monthly Load Test - Made editorial revisions and incorporated Tech. Rep.
recec=endations.
Seal Oil System - Made editorial 1-12-79 X
1 PT 27.1 - H2 changes.
1-12-79 XI O
QAP 9 - Welder Qualification - Original issue.
1-12-79 XVI 2
Annunciator Procedure A-1 (3-7), Unit No. 1 -
Adds additional requirement for torus low water level.
1-12-79 XVI 1
Annunciator Procedure A-1 (3-7), Unit No. 2 -
Adds additional requirement for torus low water level.
1-17 0 SP 79 GE Visual Examination Procedure -
Original issue.
1-17 2 SP 77 Pressure Sipping - Provides additional design information on sipper can installation locations.
1-17-75 X 13 PT 1.5.3.P - SRM Rod Blocks Channel Functional Test - Revised back to level of revision 11.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUM3ER & tin.E/ CHANGE l-17-79 X
0 PT 2.1.23PC - Shutdown Cooling Mode of RER Channel Calibration and Functional Test -
Original issue.
1-17-79 X
1 PT 1.5PC - Control Rod Withdrawal Block Channel Calibration and Functional Test - Editorial changes.
1-17-79 X
8 PT 4.1.8 - Off-Gas Hi Rad Operability Check -
Editorial changes.
1-17-79 XVI 1
2-UA-2, 4-8 Stat Coolant Outlet Temp. - High FM'78-231 reduces turbine runback temp. from 0
95 6 to 81 6 and Hi temp. alarm from 87 6 to 7606 as per GE recommendation.
1-17-79 XVI 1
2-UA-2, 1 Loss of Stator Coolant Trip Check Energized - PM 78-231 reduces turbine runback temp. from 9506 to 8106 as per GE recommendation.
1-17-79 XVI 1
2-UA-2, 3 Stator Coolant Inlet Temp. High -
FM 78-231 reduces turbine runback temp. from 9506 to 8106 as per GE recommendation.
1-17-79 X
11 PT 14.1 - Control Red Operability Check -
Editorial change.
1-17-79 VI 3
EI 37.2 - Operation during flooding conditions -
Include flooding procedure for Caswell Beach.
1-17-79 X
9 PT 8.2.4 - RER Service Water System Component Test - Add location of flow transmitters N007A
(-17' NRHR) & N0073 (-17' SRHR) to assist I&C Tech. performing PT.
1-17-79 III 10 OP 13 - Fuel Fool Cooling and Cleanup - To allow RHR to be used in parallel with fuel pool cooling to clean the reactor vessel and reactor cavity when fuel pool gates are installed and the reactor cavity is only partially flooded.
1-17-79 III 10 OP 2 - Reactor Recirculation System - Deletc 71, Pump 2A suction header test connection root C and V2, Pump 2A suction header test connection isolation C.
1-17-79 III 4
OP 37.4 - Diesel Generator Building Heating &
Ventilation System - To incorporate FECP 1378 into the OP.
1-18-79 0
SP 79 Testing and Inspection of Lifting Arrangement for Shielded Personnel Basket -
Original issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CILCCE 1
SP 79 Testing and Inspection of Lifting 1-19-79 Arrangement for Shielded Personnel Basket - Allow liquid penetrant of lifting lugs rather than mag particle.
0 SP 79 Southwest Research Institute Nondes-1-19-79 tructive Testing Procedures - Original issue.
1-20-79 XVI 1
1-A7-2-2 Annunciator Procedure - Provides reasons for high or low reactor water level giving observations and actions to be taken by personnel.
1-20-79 X
0 PT 1.1.5 - Reactor Vessel Level Indication and Alarm (Unit No. 1) - To determine operability of Control Room and refueling floor and reactor water level monitoring devices.
1-22-79 1
SP 79 Southwest Research Institute Nondes-tructive Testing Procedures - Add deviation #2 and #3 to S'JRI Procedure #600-3/46.
1-23-79 X
3 PT 19.6,0.1 - Visual Inspection of Inaccessible Snubbers on Safety-Related Systems - Revised to comply with changes as per NRC letter Serial
- RII: DGH, 50-324 and 50-325/78-25.
1-23-79 X
2 PT 19.6.0.2 - Visual Inspection of Accessible Snubbers on Safety-Related Systems - Revised to comply with changes as per NRC letter Serial
- RII: DGH, 50-324 and 50-325/78-25.
1-23-79 X
2 PT 12.4 - Diesel Generator Alar =s, Trips and Trip Bypass Tests - To incorporate PT 12.5, update per Mod.78-159, to make PT applicable for each diesel, and editorial changes.
1-23-79 7
2 PT 2.3.4 - Suppression Pool - Reactor Building Vacuum Breakers - Revised so that vacuum breaker isolation valves remain closed as per Tech. Spec.
Amendment (#16 for Unit No. 1, #41 for Unit No.
2).
1-23-79 X
6 PT 36.4 - Stator Cooling - page 2, VII C reads (2030F) (col 199.4-2060F) should read (1780F+
30F).
1-24-79 1
SP 79 In-Core Vibration Sensor and Hardware Re= oval - Add radiological precautions.
1-26-79 X
4 PT 35.5 - Fire Extinguisher & Inspection - To match extinguisher locations and types in plant.
OPERATING MANUAL PROCEDURE CEANCES REV.
DATE VOL.
50.
NUISER & TITLE / CHANGE l-29-79 XII 4
- e 6 - Operation of Cranes and Use/ Inspection of Slings - Added a new Section III, pages 14, 15, and 16.
This includes safety precautions, rigging, tool control, and emergency evacuation for the shielded personnel work basket.
1-30-79 0
SP 79 Foreign Material Retrieval - Original issue.
1-30-79 0
SP 79 Feedwater Nozzle Inspection and Repair - Original issue.
1-30-79 0
SP 79 Control Rod Drive Return Line Nozzle Inspection and Repair - Original issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE I-5-79 X
2 PT 45.1.7 - Turbine Control Valve Fast Closure-Response Time - Revised so as to monitor K8A through D on Unit No. 1.
2-5-79 X
5 PT 19.6.1 - Safety-Related Snubber Functional Testing - Revised to comply with NRC letter Serial No. RII: DGH-50-324 and 50-325/78-25 dated November 9, 1978.
2-5-79 XIX 2
FP S - Fire Protection Procedure - Fire Barrier Penetration Seal - Work Permit Control - Revised to provide definitions of terms.
2-5-79 1
SP 79-9, CRD Return Line Nozzle Inspection and Repair. Omit photographic requirements in Steps 7.3.2 and 7.3.4 and =ake photographs optional in Step 7.4.6.
2-5-79 2
SP 79-9, CRD Return Line Nozzle Inspection and Repair - Include a larger area to be inspected around the CRD nozzle.
0 SP 79 GE Procedure for Liquid Penetrant on 2-6-79 CRD Nozzles - Original issue.
2-7-79 X
0 PT 2.1.2PC - EPCI Turbine Steamline Low Pressure Calibration and Channel Fanctional Test -
Original issue.
2-7-79 X
0 PT 1.5.2PC - IRM Channel Calibration and Function-al Test - Original issue.
2-7-79 X
1 PT 12.5 - Diesel Generator Trips Bypass - delete PT - has been incorporated in PT 12.4 2-7-79 X
1 PT 1.5.3PC - Source Range Monitoring System Channel Calibration and Functional Test -
clarify steps regarding RPS refueling jumper links if remoyed during refueling.
2-7-79 X
2 PT 45.1.1 - Scram Pilot Valve Solenoids Logic Response Time - Recorder chart speed increased to make response time traces easier to read.
2-7-79 VI 9
EI 27 Abnormal Release of Radioactivity-Airborne - to provide information to operate in worst case condition.
2-7-79 III 11 OP 13 - Fuel Pool Cooling and Cleanup - to revise valve lineup to reflect actual condition.
OPERATTNG MANUAL PROCEOURE CEiNCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-7-79 X
2 PT 2.2.3 - Primary' Containment Isolation Valves Closure Timing - to delete valves already incor-porated in ISI valve tests.
2-7-79 III 2
OP 49 - Lube 011 Storage and Conditioning System - add new Section "N" to procedure. Add RFPT Lube.0il Purifiers.
2-7-79 X
5 PT 9.3A - EPCI System Cocponent Test - Revised to include Baseline Data, added torus temperature sheet.
2-7-79 III 17 OP 24 - Contain=ent Atmospheric Control System -
editorial change.
2-8-79 X
0 PT 20.6.1 - Suppression Poul Inspection - Origi-nal issue.
2-8-79 X
0 PT 15.1.1 - Standby Gas Treat =ent Heater Check -
Original issue.
2-8-79 1
SP 79 Feedwater No::le Inspection and Repair.- Made the requirements for photogra hs c
optional and'added a step for LP inspection.
2-9-79 0
SP 79 No::le Excavation Oxidation Etch -
Original issue.
2-9-79 XX 6
ENP 3 - Q-List Modifications Procedures - Changed routing of an operational plant modification so that QA reviews it earlier; recorded the number of field revisions; reviewed non-Q-List impact on Q-List items and review for unreviewed safet,y questions; =ade editorial changes.
2-12-79 II 2
SD 26 Turbine Gland Seal Steam and Drains -
Changed valve prefix from MOV to M7D.
2-12-79 III 8
OP 26 Turbine Gland and Seal System - Changed valve prefix from MOV to MVD.
2-12-79 X
0 PT 25.3P - Seismic Monitoring Peak Shock Recorder - Initial issue.
1 STP 77 Special Test for Isolation Operation 2-12-79 of the Control Rod Drive Hydraulic Return Line to the Reactor Pressure Vessel - Added data to be recorded; added informatim. and ensures double valve isolation.
2-12-79 X
8 PT 18.1 - Refueling Interlock Check - Updated and added notes referring to the Technical Specifica-tions.
OPERATING "ANUAL PROCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-12-79 IX 2
FH 11C - Fuel Handling Procedure Operational Source Removal - Revised to use the new instru-ment handling tool.
2-12-79 IX 9
FH 11 - Refueling - Revised to correct typos and to upgrade for current refueling.
2-12-79 IX 0
FH llG - Fuel Handling Procedure Neutron Source (Critical) Installation - Original issue.
0 STP 79 RPV Bottom Drain valve Inspection -
2-16-79 Initial issue.
2-21-79 VIII 1
RC&T Procedure 0009, Spent Fuel Cask Shipments -
Consolidated all surveys and reduced required signa tur es.
2-21-79 VIII 8
RC&T Procedure 0005, Radiological Environmental Monitoring Program - To add a standard form for sample collection.
2-21-79 VIII 2
RC&T Procedure 0007, Stack & Building Vent Radioactive Gaseous Release Setpoints - Revised to all'ow closed loop systems on both Turbine Buildings.
2-22-79 2
SP 79 Southwest Research Nondestructive Testing Procedures SP 79-6, Rev. 1 - Added addi-tional procedures and deviations as required to perform Unit No. 2 ISI.
2-23-79 X
11 PT 2.1.23P - Shutdown Cooling >bde of RER Channel functional Test - Revised to conform to prints.
2-23-79 XVII 4
Security Plan - Revised in accordance with comments and resolution of NRC concerns of 10CFR71.55 submittal.
2-23-79 XVII 5
Security Plan - Revised in accordance with comments and resolution of NRC concerns of 10CFR73.55 submittal.
2-23-79 XVII 19 SI 9 - Access Control and Personnel Identifica-tion - To implement 10CFR73.55 security require-ments.
2-23-79 XVII 5
SI 16 - Security Procedures to be Followed in Event of Electronic Security System Failures -
To t=plement 10CFR73.55 security requirements.
2-23-79 0
STP 14 - Function Testing of Control Rods - To reduce time for control rod friction testing.
OPERATING MANUAL PRCCEDURE CHANGES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 2-27-79 0
STP 79-15 Unit No. 2 HPCI Control Test -
Initial issue.
2-28-79 XI O
QAP 10 - Method of Documenting Removal of Book 1 Equipment for Repairs - New procedure.
2-28-79 XI 4
QAP 1 - Preparation and Control of Quality Book 1 Assurance Instructions and Procedures - To provide a means of writing joint instructions between plant QA and site ESC QC.
F I
e
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE 3-5-79 0
Special Procedure 79-16, Cracked or Damaged Operational Source Holder Removal - Initial issue.
3-5-79 X
2 PT 1.2.4A, APRM Inop - Added installation of shorting links and removal after test.
3-5-79 X
7 PT 1.2.1, Source Range Monitoring System - Added installation of shorting links and removal after test.
3-5-79 X
8 PT 1.2.3, Average Power Range Monitor - Delete.
3-7-79 XI 10 vol. XI, Book 2 Q-List - Upgrades Q-List on several syste=s.
3-7-79 XI 10 Vol. XI, Book 2 Appendix A - Q-List Drawings -
Revised Q-List drawings for several systems.
3-7-79 VIII 6
RC&T 0004, Instrument Calibration Control - Adds and deletes calibrations performed by RC&T and references use of PT computer program in schedu-ling.
3-7-79 X
0 PT 17.6, 125 Volt Battery Capacity Test - New battery capacity test as required by Standard Technical Specifications.
3-7-79 X
3 PT 45.1.4,'APRM Neutron Flux High (15% & 120%) -
Clarify difference in performing this PT in Run or Shutdown.
3-7-79 X
1 PT 5.4.lPC, Chloride Intrusion Monitor Calibra-tion - Made editorial revisions.
3-7-79 X
2 PT 45.2.15, Condenser Vacuum Low Response Time -
To allow performing this PT in the Run mode.
3-7-79 X
0 PT 5.lPC, Drywell Floor & Equipnent Drain Systa=
Channel Calibration Test - Original issue as required by Standard Technical Specifications.
3-7-79 I
5 PT 2.1.3PC, HPCI Steam Leak Detection - Add response time test switch.
3-7-79 X
0 PT 4.1.lPC, Rx 31dg. Vent Exhaust Radiation Monitoring System Channel Calibration - Original issue as required by Standard Technical Specifications.
3-7-79 III 7
OP 29-E, Circulating Water System - Correct error on Electrical Lineup Sheet.
3-7-79 III 5
OP 37.4, Diesel Generator Building HVAC System -
Revised in accordance with Plant Mod 77-358.
3-7-79 X
3 PT 12.2A, D/G #1 Monthly Load Test -Clarifies PT and general correction.
L
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE
,,0.
3-7-79 X
3 PT 12.23, D/G #2 Monthly Load Test - Clarifies PT and general correccion.
3-7-79 X
3 PT 12.2C, D/G #3 Monthly Load Test - Clarifies PT and general correction.
3-7-79 X
3 PT 12.2D, D/G #412nthly Load Test - Clarifies PT and general correction.
3-7-79 X
9 PT 4.1.8, Off Gas Hi Rad Operability Check -
Delete valves no longer activated by 15-minute timer.
3-7-79 III 18 OP 24, CAC System - Adds procedure for transfer-ring CAC Tank to the CAD Tank.
3-7-79 I
3 PT 12.6, Breaker Align =ent Surveillance - AOI.26 covers D/G Operability, operability surveillance deleted.
3-7-79 I
7 PT 19.4, Safety / Relief Valve Pressure Test - To comply with Standard Technical Specifications.
3-7-79 XII 2
MP-25, Qualifications of Weld Procedure Specifi-cations and Welders - Add weld bend test jig requirements and tolerances on the jig and coupon measurements.
3-7-79 III 17 OP 19, EPCI System - Adds precautions to take in event of fire in cable spread room.
3-7-79 III 9
OP 16, RCIC - Adds procedure for operation of RCIC from outside Control Room in accordance with Plant Modification 77-370.
2 SP 77-29, CRD Friction Testing - Adds optional 3-9-79 control rod drive scrum testing to the procedure.
3-12-79 3
SP 79-6, Southwest Research Nondestructive Testing Procedure - Adds UT Procedure SWRI-NDT-800-25 to existing procedures.
3 SP 77-16, Pressure Sipping - Generic procedure 3-12-79 rewritten by GE to include prototype 2 sipping.
3-15-79 III 17 OP 17, Residual Heat Removal System - Incorporates Plant Modification 77-370.
3-15-79 X
3 PT 18.2, Service Platform Interlock Check -
Identifies test weights and adds a precaution.
3-15-79 IX 10 FH 11, Refueling - Add precaution on updating status board in Control Room and on Refueling Floor.
L
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANCE O
3-15-79 I
23 PT 1.1.7P, Reactor Protection & Control Rod Block Test /APRM Flow - Biased (Thermal) Trip /APRM Neutron (Fixed) Trip - Adds shorting link removal step.
3-15-79 X
2 PT 1.5PC, Rod Block Monitor / Control Rod Withdrawal Block Channel Calibration & Functional Test -
Changed the procedure location of taking "as found" readings.
3-15-79 X
15 PT 1.5.2P, Control Rod Blec.ks/IRM Rod Blocks -
Added annunciators and indicators and step to recove shorting links if installed.
3-15-79 III 8
OP 43, Service Water System - Incorporates Plant Mod 77-370E.
3 79 II 6
FH 11A, Refueling Platform Operations - Added precaution not to use thehoist or trolley to move control rods over the core or fuel asse=blies.
3 79 I
9 PT 18.1, Refueling Interlock Check - Identified test, weights to correspond to Technical Specifications.
3-16-79 0
SP 79-17, Peabody Test Procedure 3.23.A.2-4 Penetrant Examination Fluorescent Dye - Original issue.
3-17-79 0
SP 79-19, GE I&SE Procedures for Feedwater Sparger Removal, Inspection and Installation -
Original issue.
3-17-79 0
SP 79-18, Procedure for Installation and Re= oval of Shielded Platform and Wall Shielding - Original issue.
3-17-79 VIII O
RC&T 0201, Calibration / Operation of ND6600 Multichannel Analyzer.
3-23-79 0
SP 79-20, Control Rod Drive Thermal Sleeve Re= oval, Inspection, and Installation - Original issue.
- -23-79 0
SP 79-21, Recovery of Dropped Jet Pu=p Nozzle Cover from Vessel (Below Core Plate) - Original issue.
3-22-79 XVII 8
SI 10, vehicular Traffic and Parking Control -
To update procedures for escorting undesignated vehicles in protected and vital areas.
3-23-79 X
7 PT 5.1, Drywell Drain Su=ps Integrator Test -
Deletes PT as this functional test is included on the control operators DSR.
OPERATING MANUAL PROCEDURE CHAbc.
DATE VOLUME NUMBER & TITLE / CHANGE O
3-23-79 X
0 PT 55.4PC, Drywell Hydrogen and Oxygen Channel Calibration - To meet Standard Technical Specification require =ents.
3-23-79 X
1 PT 56.5PC, Post-Accident Reactor Pressure Inst.
Loop Calibration - Includes 13 psig head correctior when calibratir B21-PI-R004A and B.
3-27-79 IX 6
FH 15, Loading and Unloading the IF-300 Spent Fuel Cask with 3WR Fuel - Adds Technical Specification valves for the test weights.
3-27-79 IX 12 FH 9, New Fuel Receiving and Inspection - Cor-rected typos made in electrical lineup.
3-27-79 XVI O
AP A-1 (3-4), Unit Nos.1 and 2 - HPCI Room Door Open - Adds new annunciator procedure to keep the UPCI room door closed.
3-27-79 2
STP 77-4, Special Test for Isolated Operation of the Control Rod Drive Hydraulic Return Line to the Reactor Pressure Vessel - Adds to data sheet for two pump operation, previous te=porary revisions and one instru=ent to calibrate.
3-27-79 3
STP 79-7, Control Rod Drive Return Line Nozzle Inspection and Repair - Deleted section that is to be perfor=ed as the thermal sleeve will not be installed.
3-30-79 X
5 PT 14.2.1, Single Rod Scram Insert. >n Time Test -
Made editorial changes and revis ' is due to sof t-ware changes.
3-30-79 I, Bk.2 12 AI 12, Plant Filing Instruction - Revised per RC&T request for file nu=bers and retention of their calibration records and revised retention of PT's to lifetime in response to surveillance OQAS 79-38, 3-30-79 X
1 PT 20.6, Drywell to Torus Leak Rate Test - Made editorial revisions concerning test equipment and valve lincup.
3-30-79 XVII 5
SI 2, Civil Disturbance - To update per new Security Plan.
3-30-79 XVII 3
SI 14, Support from Off-Site Agencies - Updates telephone number.
3-30-79 X7II 2
SI 17, Industrial Security Alerts - Updates telephone nu=ber.
3-30-79 XIX 1
FP 1, Plant Fire Brigade - Updates composition of the Fire Brigade, e
f m
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE / CHANGE 4-2-79 VI 6
EI Clarify procedure.
4-2-79 III 10 CP Duplicate lineup sheets.
(temp.
STP-79 To allow use of grapples with red 4-2-79 rev.)
50-19 pulled out of the core.
4-2-79 VI 4
EI Make it easy to read.
4-2-79 III 5
OP-37.3 - Includes Turb. Building chiller.
4-2-79 X
2 PT 35.2 - To reflect changes due to Mods.77-350 and 77-367.
4-2-79 X
4 PT 1.1.12PC - To reflect changes due to Mod.78-221.
4-2-79 X
4-2-79 X
3 PT 1.1.9PC - Clarify valving procedure of flow transmitters.
4-2-79 X
24 PT 1.1.7P - To include requirement of Tech.
Spec. Table 4.3.1-1, 2.b.(f).
4-3-79 X
2 PT 12.1.1 - Diesel Generator Actual Loading Test -
Revised Section 'A' and added Section 'D' to i= prove the =ethod of testing to ensure testing is within the technical specifications.
4-4-79 0
SP 79 Inspection and Testing Procedure for Concrete Expansion Anchors - Initial issue.
4-4-79 X
4 PT 31.3 - Noninterruptible Instrument Air System Test - Revised to s1=plify test and obtain more realistic results.
4-4-79 X
10 PT 18.1 - Refueling Interlock Check - Updates PT to include testing the fra=e and monorail hoists prior to moving control rods in the core.
4-4-79 X
1 PT 50.3 - TIP Reproducibility - Updates per latest technical data.
4-4-79 X
5 PT 14.3 - Shutdown Margin - Revised method of demonstration of shutdown margin.
4-4-7, X
0 PT 50.3.1 - Total TIP. Uncertainty - Original issue.
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE O
4-4-79 X
3 PT 14.5.2 - Reactivity Anomaly Check - Made editorial corrections and defined cycle exposure in terms of P2 core average exposure.
4-4-79 X
1 PT 50.1 - LPRM/APRM Initial Sensitivities -
Procedure revised to include initial sensitivitien for model NA-200 LPRM detector.
4-4-79 X
0 PT 50.12 - Measurement of In-Sequence Critical Data - Original issue for post refueling startup testing.
4-4-79 X
2 PT 50.5 - Total Core Flow Calibration - Made editorici corrections and allowed use of process cceputer for core flow calibration.
4-4-79 X
9 PT 1.9 - LPRM Calibration - Made editorial corrections and added an optional OD-8 to calibrated LPRM readings if desired.
4-4-79 XII 2
MP Corrective Maintenance Procedure - To allow work request and authorization to be signed by the refueling SRO and Lead I&C Mechanic for emergency repairs on the refueling floor only.
4-4-79 XVII 6
SI-l - Bomb Threats - Updates telephone numbers.
4-4-79 XX 0
ENP Piping Isometric Drawings - Original issue (was ENI-13).
4-4-79 X
1 PT 17.6 - 125 Volt Battery Capacity Test - The HRD Tester cannot be connected directly to the battery charger without the battery being connected as. voltage spikes.from the charger will damage.the HRD Tester.
4-4-79 X
4 PT 2.3.3 - Drywell Vacuum Breakers - Added new
" Figure 1" showing setpoint and adjustment.
4-4-79 X
1 PT 2.1.16PC - RWCU Righ Flow Channel Calibration
& Functional Test - Table on page ten contained incorrect value. The error was discovered while perfor=ing the PT for the first ti=e.
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE O
4-4-79 VIII 2
RC&T Procedure 0006 - Sa=pling and Analysis Schedule for Environmental Technical Specification Items - To make the procedure consistent with current operating practice.
4-4-76 VIII 17 RC&T Procedure 0002 - Sa=pling and Analysis Schedule for Radioactive and Nonradioactive Chemistry - To include a schedule for sampling the makeup water carbon filter. This was at the recoc=endation of the CP&L Chemistry Subunit in Raleigh.
4-6-79 X
3 PT 1.1.3XC - High Drywell Pressure Channel Calibration and Functional Test. Delete 1.1.3XC.
Plant Mod.77-150 has been completed on Unit No.
L PT 1.1.3PC will now be used for both units.
4-6-79 X
5 PT 1.1.4X - Reactor Low Water Level #1 Channel Functional Test.
Delete PT 1.1.4X.
Plant Mod.
77-27 has been completed on Unit No. 1.
PT 1.1.4P will now be used for both units.
4-6-79 X
2 PT 1.1.4XC - Reactor Low Water Level #1 Channel Calibration and Functional Test. Delete PT 1.1.4XC.
Plant Mod. 77-27 has been completed on Unit No. 1.
PT 1.1.4PC will now be used for both units.
4-6-79 X
3 PT 1.1.3X - High Drywell ?ressure Channel Functional Test. Delete PT 1.1.3..
Plant Mod.77-150 has been completed on Unic No. 1.
PT 1.1.3P will now be used for both units.
4-6-79 XIII 10 E=ergency Plan - The County Sheriff's office is no longer in Southport.
It is now in Bolivia.
(Also, Civil Preparedness Coordinator's office is now located in Bolivia.)
4-6-79 X
1 PT 35.4.4 - Fire Detection System - To reflect changes in system due to installation of Plant Mod.77-357 and 77-368.
0 Special Test Procedure 79 Condenser Inleak-4-6-79 age Testing - To allow condenser inleak testing.
1
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE / CHANGE 0.
4-6-79 X
3 PT 6.2.3 - SLC Injection Test - To add steps to prevent firing both squib valves and change maintenance instruction reference.
4-6-79 XVI O
Annunciator Procedure - Panel UA-38, Unit No. 1, List of Effective Precedures.
4-6-79 XVI 0
AP UA-38 (1-1) - Reactor Building Send. Pipe System Pressure Low.
4-6-79 XVI O
AP UA-38 (1-2) - Reactor Building SPR System Pressure Low.
4-6-79 XVI 0
AP UA-38 (1-3) - R3 El 80 E SPR System Flov.
4-6-79 XVI O
AP UA-38 (1-4) - R3 20 NE SPR System Flow.
4-6-79 XVI O
AP UA-38 (1-5) - RB El 20 SW SPR System Flow.
4-6-79 XVI 0
AP UA-38 (2-1) - Reactor Building Stnd. Pipe System Flow High.
4-6-79 XVI O
AP UA-38 (2-2) - Reactor Building SPR System Flow High.
4-6-79 XVI O
AP UA-38 (2-3) - R3 El 50 NE SPR System Flow.
4-6-79 XVI 0
AP UA-38 (2-4) - R3 El-17 NE SPR System Flew.
4-6-79 XVI 0
AP UA-38 (2-5) - Reactor Building El-17 SE SPR System Flow.
4-6-79 XVI O
AP UA-38 (3-1) - Reactor Building Send. Pipe System Flew.
4-6-79 XVI 0
AP UA-38 (3-2) - Spare 4-6-79 XVI O
AP UA-38 (3-3) - R3 SBGT A Int. SPR System Flow.
4-6-79 XVI O
AP UA-38 (3-4) - R3 El-17 NW SPR System Flow.
4-6-79 IVI O
AP UA-38 (3-5) - R3 El-17 SW SPR System Flew.
4-6-79 XVI O
AP UA-38 (4-1) - Reactor Building Stnd. Pipe System Del. Valve Open.
4-6-79 XVI 0
AP UA-38 (4-2) - Reactor Building SPR System Del. Valve Open.
1
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE / CHANGE 4-6-79 XVI O
AP UA-38 (4-3) - R3 SBGT 3 Int. Flow System.
4-6-79 XVI O
AP UA-38 (4-4) - Spare 4-6-79 XVI O
AP UA-38 (4-5) - Spare New procedures written for newly installed annunciator panel.
4-6-79 XVI O
Annunciator Procedure Panel UA-39, Unit No. 2, List of Effective Procedures.
4-6-79 XVI O
AP UA-39 (1-1) - Reactor Building Stnd. Pipe System Pressure Low.
4-6-79 XVI O
AP UA-39 (1-2) - Reactor Building SPR System Pressure Low.
4-6-79 XVI O
AP UA-39 (1-3) - R3 El 80 E SPR System Flow.
4-6-79 XVI O
AP UA-39 (1-4) - R3 20 NE SPR System Flow.
4-6-79 XVI O
AP UA-39 (1-5) - R3 El 20 SW SPR System Flow.
4-6-79 XVI 0
AP UA-39 (2-1) - Reactor Building Stnd. Pipe System Flow High.
4-6-79 XVI O
AP UA-39 (2-2) - Reactor Building SPR System 6
Flow High.
4-6-79 XVI O
AP UA-39 (2-3) - R3 El 50 NE SPR System Flow.
4-6-79 XVI O
AP UA-39 (2-4) - R3 El-17 NE SPR System Flow.
4-6-79 XVI 0
AP UA-39 (2-5) - Reactor Building El-17 SE SPR System Flow.
4-6-79 XVI O
AP UA-39 (3-1) - Reactor Building Send. Pipe System Flow.
4-6-79 XVI 0
AP UA-39 (3-2) - Spare 4-6-79 XVI O
AP UA-39 (3-3) - RB SBGT A Int. SPR System Flow.
4-6-79 XVI O
AP UA-39 (3-4) - R3 El-17 NW SPR System Flow.
OPERATING MANUAL PRCCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE O
4-6-79 XVI O
AP UA-39 (3-5) - RB El-17 SW SPR System Flow.
4-6-79 XVI 0
AP UA-39 (4-1) - Reactor Building Stnd. Pipe System Del. Valve Open.
4-6-79 XVI 0
AP UA-39 (4-2) - Reactor Building SPR System Del. Valve Open.
4-6-79 XVI O
AP UA-39 (4-3) - R3 SBGT B Int. SPR System Flow.
4-6-79 XVI 0
AP UA-39 (4-4) - Spare 4-6-79 XVI O
AP UA-39 (4-5) - Spare New procedure written for newly installed annunciator panel and fire protection system.
4-6-79 X
1 PT 20.6.1 - Interior Suppression Pool & Exterior Suppression Enclosura Inspection - Added the inspection of the suppressicn chamber enclosure.
4-6-79 3
STP 77 Test Instruction for Isolated Operation of the Control Rod Drive Hydraulic Return Pipe to the Reactor Pressure Vessel - Added a prerequisite that all rods do not have to be inserted or "one rod out" interlock when all fuel was removed from the core.
4-10-79 IV 43 GP General Plant Operating Procedure - Updates procedure and adds Unit No. 1 A-2 and B-2 sequence sheets for cycle 2 per GE CMR.
4-10-79 III 5
OP Fire Protection System - Incorporates valves installed per fire protection modifications 4-10-79 III 11 OP Control Rod Drive System - Adds section concerning operation of the CRD return line.
4-10-79 III 9'
OP Nuclear Boiler - Corr ~ects valve lineup.
4-10-79 III 10 OP RCIC System - Corrects electrical lineup.
4-10-79 III 3
OP Circulatinz Water System - Corrects electrical lineup.
4-10-79 XVI O
AP UA-36 (1-6), Unit No. 2 Reactor Building Spr.
System Pressure Low - Original issue.
1
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE / CHANGE O
4-10-79 XVI O
AP UA-36 (1-7), Unit No. 2 Reactor Building Stnd.
Pipe System Pressure Low - Original issue.
4-10-79 XVI O
AP UA-36 (1-8), Unit No. 2 RB El 80 E Spr. System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (1-9), Unit No. 2 Spare 4-10-79 XVI 0
AP UA-36 (2-6), Unit No. 2 Reactor Building Spr.
System Flow High - Original issue.
4-10-79 XVI O
AP UA-36 (2-7), Unit No. 2 Reactor Building Stnd.
Pipe System Flow High - Original issue.
4-10-79 XVI 0
AP UA-36 (2-8), Unit No. 2 RB El 50 NE Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (3-7), Unit No. 2 Reactor Building Stnd.
Pipe System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (3-8), Unit No. 2 RB SBGT A Int. Spr.
System Flow - Original issue.
4-10-79 XVI 0
AP UA-36 (3-9), Unic No. 2 R3 SBGT B Int. Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (4-4), Unit No. 2 Spare.
4-10-79 XVI O
AP UA-36 (4-5), Unit No. 2 Spare.
4-10-79 XVI O
AP UA-36 (4-6), Unit No. 2 Reactor Building Spr.
System Del. Valve Open - Original issue.
4-10-79 XVI O
AP UA-36 (4-7), Unit No. 2 Reactor Building Stnd.
Pipe System Del. Valve Open - Original issue.
4-10-79 XVI 0
AP UA-36 (4-8), Unit No. 2 R3 El 20 NE Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (4-9), Unit No. 2 R3 El 20 SW Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (5-4), Unit No. 2 Spare.
4-10-79 XVI 0
AP UA-36 (5-5), Unit No. 2 Spare.
OPERATING MANUAL PROCEDURE CHMiGES DATE VOLUME NUMBER & TITLE /CHMiGE 4-10-79 XVI O
AP UA-36 (5-6), Unit No. 2 Spare.
4-10-79 XVI O
AP UA-36 (5-8), Unit No. 2 R3 El-17 NE Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (5-9), Unit No. 2 R3 El-17 SE Spr.
System Flow - Original issue.
4-10-79 XVI O
AP UA-36 (6-5), Unit No. 2 Spare.
4-10 '9 XVI O
AP UA-36 (6-6), Unit No. 2 Spare.
4-10-79 XVI O
AP UA-36 (6-7), Unic No. 2 Spare.
4-10-79 XVI O
AP UA-36 (6-8), Unit No. 2 R3 El-17 NW Spr.
Systen Flow - Original issue.
4-10-79 XVI O
AP UA-36 (6-9), Unit No. 2 R3 El-17 SW System Flow - Original issue.
4-11-79 X
1 PT 56.2PC - Suppressien Chamber Level Loop Calibration - Revised head connection Yor 1-CAC-LT 2601 and 2602 and revised in accordance with Plant Mod.77-370.
4-11-79 X
4 PT 1.2.3PC - APRM Channel Calibration (15%) -
Revised per technical specification change.
4-11-79 X
16 PT 1.5.2P - Control Rod Blocks - Revised to agree with technical specification requirements.
4-11-79 X
6 PT 1.1.7PC - APRM Channel Calibration - Rewritten to simplify procedure.
4-11-79 X
3 PT 3.1.14XC - ECCS Reactor Low Pressure Channel Calibration and Functional Test - Revised in accordance with Plant Mod.77-149.
4-11-79 X
0 PT 56.1PC - RER and Core Spray System Pump Start Time Delay Relays Calibration - Original issue.
4-11-79 X
3 PT 45.3.5 - LPCI Initiation Response Ti=e - Made editorial revisions.
4-11-79 X
1 PT 17.11P - Spare Plant Batteries - Revised to include obtaining lost specific gravity reading and editorial changes.
\\
OPERATING MANUAL PROCEDURE CHANCES DATE VOL'IME NUMBER & TITLE / CHANGE O
4-11-79 X
1 PT 55.4PC - Drywell Hydrogen and oxygen Channel Calibration - Revised setpoints and made editorial changes.
4-11-79 XVI O
AP UA-36 Panel - Original issue.
4-11-79 0
SP 79 Control Rod - Removal and Installation -
Original issue.
4-12-79 X
10 PT 1.2.3 - Average Power Range Monitor. (15") -
Procedure reactivated.
4-12-79 X
4 PT 12.6 - Breaker Alignment Surveillance - To cemply with OQA coc=ents.
4-12-79 X
3 PT 12.2.1 - ECCS D/G Logic Test - Revised time tolerance and provides time colu=n.
4-12-79 X
9 PT 2.1.22 - Steam Line Area High Temperature -
Delete require =ents for reactor mode switch to be in run.
4-12-79 8
SP 76 Reactor Leak Check - Made editorial revisions concerning sequence of valve operations.
4-12-79 III 7
OP 26 EHC Hydraulic System - Corrects valve lineup.
4-12-79 III 7
OP Instrument and Service Air - Corrects valve lineup.
4-12-79 III 12 OP Control Rod Drive - Revised Flow Controller Range in accordance with technical specification change.
4-12 -7 9 III 3
OP Generator and Exciter System - Corrects electrical lineup.
4-12-79 III 20 OP Reactor Recirculation. System - Corrects pump labeling.
4-12-79 XVI 1
AP UA-15 (2-1) - Bus El Undervoltage - Revised in accordance with Plant Mod.77-327.
4-12-79 XVI 1
AP UA-16 (2-1) - Bus E2 Undervoltage - Revised in accorde.nce with Plant Mod.77-327.
~
OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE 4-12-79 XVI 1
AP UA-17 (2-1), Bus E3 Undervoltage - Revised in accordance with Plant Mod.77-327.
4-12-79 XVI 1
AP UA-18 (2-1) - Sus E4 Undervoltage - Revised in accordance with Plant Mod.77-327.
4-12-79 XVI 2
AP A-5 (5-5), Unit No. 1 Pri=ary Containment Hi Flow Pressure Alarm - Revised per technical specification change.
4-12-79 XVI 2
AP A-5 (5-5), Unit No. 2 Primary Containment Hi Flow Pressure Alarm - Revised per technical specification change.
4-12-79 X
10 PT 1.5.1 - Rod Block Monitor - Revised per technical change No. 23.
4-12-79 X
2 PT 50.0 - Post Refueling Outage - Revised due to changes in CRD, Shutdown Margin, TIP uncertainty and critical valve testing.
4-13-79 II 2
SD Reactor Recirculation System - Revised setpoint in accordance with Plant Mod.79-031.
4-13-79 X
5 PT 1.1.8PC - APRM Rod Block Channel Calibration -
Revised per technical specification change.
4-13-79 XII 4
MP Maintenance Periodic Testing Procedure -
Delete. Procedures are covered in Volume 1, Administrative Procedures.
4-13-79 0
STP 79 Control Rocm Emergency Filters In-Place Test - Original issue.
1 SP 79 Inspection and Testing Procedure for 4-13-79 Concrete Expansion Anchors - Incorporated changes identified by AE and added list of hangers and CP&L QA requirements.
4-19-79 X
1 PT 3.2 - Recir. Pu=p Trip Logic Functional Test -
Adds testing of auxiliary trip logic to annunciator test.
4-19-79 X
12 PT 1.11 - Core Performance Para =eter Check -
Incorporates PT 1.8 and updates for new cycle for both units.
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE /CEiNGE O
4-19-79 X
2 PT 1.9D - TIP System Calibration - Revised per latest technical infor=ation.
4-19-79 X
3 PT 1.5PC - Rod Block Monitor - Revised in accordance with Plant Mod.79-055.
4-19-79 X
0 PT 26.1PC - Seismic Monitoring System Time-History & Peak Shock Recorders Calibration Test -
Original issue in accordance with Standard Technical Specifications.
4-19-79 1
STP 79 RPV Bottem Valve Inspection e Revision 1 does not attempt to clear line with a rooter tool. Allows RWCU to be in operation.
4-20-79 1
STP 79 Friction Testing of Control Rods -
Adds a data table to condense and correlate test data.
4-20-79 4
STP 77 Special Test for Isolated Operation of the CRD Return Line to the Reactor Vessel -
Omitted steps to be performed on the second unit.
4-24-79 III 5
OP Standby Liquid Control System - Revised in accordance with Plant Mod.78-162.
4-24-79 III 4
OP Core Spray System - Revised in accordance with Plant Mod.77-149.
4-24-79 III 23 OP Reactor Water Cleanup - Revised in accordance with recent Plant Modification.
4-24-79 III 11 OP-50.1 - Diesel Generator Emergency' Power System - To conform with FECP 1350.
4-2'4-79 III 19 OP CAC System - Revised in accordance with Plant Mod.78-260.
4-24-79 III 5
OP Diesel Generator - Corrects errors in valve lineup.
4-24-79 IV 42 GP General Operating Procedure - Deletes RCR Loop Te=perature readings from cceputer which are below instrument ranges.
L
S
~
OPERATING MANUAL PROCEDURE CHANGES DATE VOLUME NUMBER & TITLE / CHANGE 4-24-79 X
2 PT 6.2.2 - SLC Recire. with Borated Water - delete Incorporated into PT 6.2.3.
4-24-79 X
4 PT 6.2.3 - SLC Injection Test - Incorporates into PT 6.2.2.
4-24-79 X
4 PT 24.2 - CAM Component Test - Corrects procedure and adds penetration nu=ber of valves.
4-24-79 X
7 PT 11.1.2 - ADS Valve Test - Clarify bypass valve openings.
4-24-79 III 18 OP RHR System - Revised valve lineup for F05LA & 3.
4-26-79 X
20 PT 1.1.12P - Eigh Steamline Radiation Channel Functional Test - Makes editorial revisions and uses pico-a=p source to set alarms for higher accuracy.
4-30-79 XI 5
QAP On-Site QA Sursaillance - Adds. provision for escalation in the event resolution of surveillance reports cannot be reconciled.
4-30-79 X
0 PT 35.21 - E=ergency Lighting System - To meet FSAR ce=siement.
4-30-79 X
6 PT 14.3 - Shutdown Margin - Corrects typographical error.
4-30-79 X
2 PT 50.2 - SRM/IRM/APRM Overlap - Revised to require minimum of channels required and verifies 5 CPS.
overlap prior to 5 X 10 e
OPERATINC f tANUAL PROCEDURE CTIANCES REV.
DATE VOL.
NO.
NL7!BER & TITLE /Cl!ANCE 5-2-79 IV 45 GP General operating Procedure - Adds cycle 3 rod withdrawal sequence 32.
3 SP 77 Control Rod Sequence Exchange - To 5-2-79 clarify power level range for sequence exchange.
0 SP 79 Recirculation Pump Trip Test -
5-2-79 Initial issue 5-3-79 X
0 PT 35.22 - Fire Suppression Water System Valve Operability Test - New PT to meet Tech. Spec.
Section 4.7.7.1 requirements, Units ill and 2.
5-4-79 X
14 PT 1.5.3P - Control Rod Blocks - SRM Rod Blocks Channel Functional Test - Added statement specifying the number of operable channels required and a line for the Shift Foreman's permission to test.
5-4-79 X
25 PT 1.1.7? - Reactor Protection and Control Rod Block Test - ARPMs - Adced clarification changes..
5-4-79 III 4
0F 27 Generator Stator Cooling System -
Added assignment of pcwer sources.
5-4-79 X
PT 1.1.14PC - Reactor Protection System MG Set Channel Calibration - New PT.
5-8-79 X
5 PT 46.1 - Locked Valves - Added CRD return valves and corrected types.
5-8-79 X
3 PT 1.3 - APRM Calibratidn - Revised the frequency.
5-8-79 XX 0
ENP Software Changes to the Process Computer New procedure to ensure the process computer software changes are reviewed.
5-8-79 X
1 PT 50.9 - Axial and Radial Core Power Distribution
- Incorporates previous temporary revisions and changes to PT 1.9D and M.I. 3 on TIP system calibration and setup.
5-8-79 X
4 PT 14.5.2 - Reactivity Anomaly Check - Revised to use both " Control Rod Density vs Exposure" and
" Control Rod Notch Position Inserted vs Exposure" on the reactivity anomaly curves.
5-9-79 X
4 PT 2.3.2 - Reactor Building to Torus Vacuum 3reakers - Revised in accordance with recent Technical Specification change.
OPERATTMC ttANUAL PRCCEDURE C11ANCES REV.
DATE VOL.
NO.
NUIDER & TITLE /CIIANCE 5-9-79 III 21 OP Reactor Recirculation System - Revised electrical lindup per Plant Mod.78-076.
5-11-79 III 6
OP Fire Protection System - Added diesel generator standpipe system and reactor building
!/2 standpipe system.
5-21-79 XVII 6
SI Locks and Key Procedure - Revised in accordance with latest change in security plan.
5-25-79 III 9
OP Circulating 'Jacer Systems - Replaces with procedure for flushing the new debris filters.
5-25-79 III 6
OP Diesel Generator - Incorporates Plant Mod.77-369 (fire protection).
3-25-79 III 11 OP-16E - Electrical Lineup - To make OP conform to LL & Elementary wiring diagrams Unic No. 2).
5-25-79 III 13 OP-32E - Electrical Lineup - Revised Unit No. 2 electrical lineup to read the same format as the Unit No. 1 electrical OP for greater ease in doing the lineup.
3-25-79 III 13 OP CRD - Revised to comply with valve lineup OP-7-V, page 6 of 23.
5-25-79 III 19 OP RHR - Allows opening of E11-F010 cross connect valve when warming up "A" RHR loop.
5-25-79 III 4
OP-27-E - Generator & Exciter - To make electrical lineup conform to LL & Elementary wiring diagram.
5-25-79 III 5
OP-18-E - Core Spray - Power supply is listed as panel 8B (which is the power supply for PCB 28A in the switchyard) and should be listed as breaker 4 on DC panel 4B.
5-25-79 III 8
OP Hester Drains - Valve Lineup - Change positions for 2-HD-V17 & 2-HD-PT-100 from closed to open and add pages 46 and 47 which were previously omitted.
5-25-79 III 3
OP-46-V - Instrument & Service Air Systems - Adds following: Valves 2-IA-V384 instru=ent air to radwaste - open, a-IA-V203 instrument air to radwaste - open.
5-25-79
!T.I 3
OP-49-E - Lube Oil Storage & Conditioning System
- Change panel 2DTA/CKT to 2TA/CKT4 and change panel 2DTA/CKT27 to 2TA/CKT27 to agree with latest LLs. Also, change panel 2DTD "A" CKT17 to 2TD "A" CKT17 and panel 2DTD "B" CKT2 to 2TD "B" CKT2.
9 OPERAT7NC ffANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NU1GER & TITLE /C11ANGE 5-25-79 III 24 OP Reactor Water Cleanup - To minimi:e airborne problems in the reactor building and new temperature versus flow limitations.
5-25-79 IV 10 OG Tech. Spec. Limit Worksheet - Clarify part II Noble Gas.
3-25-79 I
9 PT 6.1 - Standby Liquid Control System Co=ponent Test - Added a second check to verify SLC squib valve continuity.
5-25-79 X
3 PT 1.5.4 - APRM Inop. & Upsacle - Typo correction.
5-25-79 X
11 PT 1.5.1 - REM - Reflect changes in setpoints due to new core load.
Plant Mod.79-056, Unit No. 2.
5-25-79 X
13 PT 1.2.4 - APRM High Flux & Downscale Test -
Reflect Tech. Spec. requirements and OQA report.
5-25-79 X
5 PT 24.2 - Containment Atmosphere Monitoring Syster Component Test - Corrected mistake in stem verifi-cation column. Delete N.A. for entire column.
5-25-79 X
2 PT 16.1.1 - Containment Atmosphere Control System Component Test - Change the baseline value after valve maintenance during the refueling outage.
5-25-79 X
6 PT 9.3.a - HPCI System Component Test - Minimum flow calls for HPCI lineup on CST which would fil:
torus with CST water. Need revision for torus to torus lineup.
5-25-79 X
1 PT 46.0 - Cold Shutdown Valve Operability Test -
Add Acceptance Criteria and Tech. Spec. times.
5-25-79 X
1 PT 1.2.1.a - Source Range Monitoring System -
Adds a new step to check under-vessel pla? form when under-vessel work has been performed.
5-25-79 X
13 PT 10.2 - RCIC - Change baseline Unit No. 2 stroke times for F010 to 17 seconds, F019 to 10 seconds, F013 to 14 seconds, F045 to 10 seconds, and F046 to 17 seconds. Change Unit No. 1 valve F045 to 10 seconds.
3-25-79 X
6 FP 46.1 - Locked Valves - CRD F087 CRD return valve inboard isolation is to be lef t open so as to comply with OP-7 section on emergency operatiot of CRD return line to reactor vessel and valve lineup OP-7-V, page 6 of 23.
OPERATTUC !MNUAL PROCEDUitE C11ANCES REV.
DATE VOL.
NO.
NUISER & TITLE / CHANGE 5-25-79 X
3 PT 1.2.1 - Source Range Monitoring System - Adds a step to verify the position of under-vessel platform if under-vessel work has been performed.
5-25-79 I
16 AI-l - Material Kequisition, Receiving and Storage Book 2
- Revises approval level from computer generated reorders due to having an approved sotek level.
5-25-79 X
0 PT 56.6PC - Post Accident Containment Pressure Loop Calibration - Original issue in accordance with Plant Modification 77-370G.
5-25-79 X
4 PT 55-3PC - Reactor Vessel Level Loop Calibration
- Revised in accordance with Plant Mod.77-370.
5-25-79 X
2 PT 55.lPC - Drywell Pressure Loop Calibration -
Revised in accordance with Plant Mod.77-370.
5-25-79 X
4 PT 1.5PC - Rod Block Monitor - Revised setpoints as per Plant Mod.79-056.
5-25-79 X
13 PT 2.1.4? - Reactor Low Water Level #2 - Revised in accordance with Amendment #24 (Unit No. 1) and Amendment #43 (Unic No. 2) to the Technical Specifications.
5-30-79 X
9 PT 9.3 - HPCI 165 PSIG Flow Test - Corrects valve number, adds new discharge pressure and removes redundant step.
5-31-79 X
7 PT 1.10 - SRM/IRM Detector Position and Rod Block
- Adds step to check position of under-vessel platform if work has been performed under-vessel.
5-31-79 X
10 PT 8.2.4 - RHR Service Water System Component Test
- Revised baseline values.
5-31-79 X
14 PT 9.2 - HPCI System Component Test - Revises method of throttling to obtain required pressure.
5-31-79 X
3 PT 12.1.1 - Diesel Generator Actual Load Test -
Corrects editorial error.
0 SP Inspection Procedure for Seismic Supports 5-31-79
- Original issue.
5-31-79 XIX 0
FP Fire Suppression System Valve Control
- Original issue.
OPERATING MANUAL PROCEDURF. C11ANCES REV.
DATE VOL.
NO.
Nin!3ER & TITLE /CIIANGE 6-7-79 III 12 OP Heater Drain Vents and Level Control -
I=ple=ent change from nor=al position of 1-CDD-V121 from throttled to closed and delete 1-RD-V69.
6 79 III 9
OP Condenser Air Removal System - Revised valve lineup. and =ade editorial revisions.
6-7-79 III 18 OP HPCI System - Deletes pressure control valve and relief valve from valve lineup.
6-7-79 IX 11 FH Refueling - Revised step for loading fuel loading chambers (FLCs).
6-7-79 VI 7
EI Recirculation Pu=p Trip - Revised in accordance with Plant Mod.78-076.
6-7-79 VI 7
EI Low System Frequency - Revised in accordance with Plant Mod.78-076.
6-7-79 X
9 PT 9.5 - EPCI 1000 PSIG Flow Rate Test - Adds requirement to get Shif t Foreman's per=ission prior to performing PT.
6-7-79 X
10 PT 9.3 - HPCI 165 PSIG Flow Rate Test - Add sheet to E41-F006 and add require =ent to obtain Shift Foreman's permission prior to performing PT.
6-7-79 X
5 PT 2. 3.2 - Reactor Building to. Torus Vacuum Breakers - Adds require =ent to get Shift Foreman's permission prior to performing PT.
6-7-79 X
5 PT 6.2.3 - SLC Injection and Flow Rate Test - Add verification of which squib valve to be tested by checking previous PT in the vault and adds requirement to get Shif t Foreman's permissien prior to perfor=1ng PT.
6-7-79 X
2 PT 31.5 - Instrument Air System Component Test -
Corrects valve number and adds baseline data for Unit No. 1 and Unit No. 2.
6-7-79 X
6 PT 2.3.1 - Drywell to Suppression Cha=ber Vacuum Breaker - Adds require =ent to get Shif t Fore =an's permission prior to performing PT.
6-7-79 X
10 PT 13.1 - Jet Pump Operability - Made editorial changes.
6-7-79 X
2 PT 6.2.1 - 5LC R'elief Valve Test - Adds requirement to get Shif t Foreman's per=1ssion prior to performing PT.
OPERATT!!C MANUAL PROCEDURE CHANCES REV.
DATE VOL.
50.
NUMBER & TITLE / CHANGE 6 79 X
2 PT 37.2.1 - Reactor Fe -dpump Governor and Trip Mechanical Test - To show which turbine is being tested.
6-7-79 X
13 PT 40.2.5 - Turbine Control Valve Testing -
Revised in accordance with Plant Mod.78-076.
6-7-79 X
3 PT,40.2.6 - Turbine Overspeed Trip Test -
Revised equipment list.
6-7-79 III 12 OP-50 Diesel Generator Esergency Power System - Revised in accordance with Plant Mod.75-412 (ECP-0003).
6-7-79 XVI O
AP A-4 (3-8) - Recire. A Trip High Press / Low Level - Original issue in accordance with Plant Mod. 77-85.
6 79 XVI O
AP A-4 (4-8) - Recire. Pump A Trip in Test -
Original issue in accordance with Plant Mod.
77-85.
6-7-79 XVI O
AP A-4 (5-3) - Recire. Pump B Trip High Press /
Low Level - Original issue in accordance with Plant Mod. 77-85.
6-7-79 XVI 0
AP A-4 (6-8) - Recire. Pump B Trip in Test -
Original issue in accordance with Plant Mod.
77-85.
6-7-79 XVI 1
AP A-5 (1-3) - SRM Downscale - Revised technical specification reference.
6-7-79 XVI 1
AP A-5 (1-4) - IRM Downscale - Revised setpoint.
6-7-79 XVI 1
AP A-5 (1-6) - Discharge Vol. Hi Water Level CRD Trip - Revised setpoint in accordance with Plant Mod.76-143.
6-7-79 XVI 1
AP A-5 (2-3) - SRM Upscale /Inop. - Corrects note and technical specification reference.
6-7-79 XVI 1
AP A-5 (3-2) - Rod Drif t - Revised technical specification reference.
6-7-79 XVI 1
AP A-5 (3-6) - Reactor Vessel Hi Pressure Trip -
Corrects setpoint.
6 79 XVI 1
AP A-5 (3-7) - Main Steam Line Ri/H1 Rad Trip -
Reviewed setpoint in accordance with Plant Mod.76-138.
OPERATTMC IWIUAL PROCEDURF. Cl!ANCES REV.
DATE VOL.
NO.
NLTBER & TITLE /Cl!ANCE 6-7-79 XVI 1
AP A-5 (3-8) - A Rods Bypassed - Revised technical specification reference.
6-7-79 XVI 1
AP A-5 (4-3) - SRM DET Retract Not Permi.tted -
Revised technical specification reference.
6 79 XVI 1
AP A-5 (4-8) - J Rods Bypassed - Revised technical specification reference.
6-7-79 XVI 1
AP A-5 (5-8) - All A/3 Sequence Rods Not Full Out - Revised technical specification reference.
6-7-79 XVI 1
AP A-5 (6-6) - Turbine Control Valve Fast Closure Trip - Updated and corrects technical specification reference.
6-7-79 XVI 1
AP A-5 (6-7) - Turbine Control Valve Fast Closure and Turbine Stop Valve Trip Bypass - Corrects setpoint and technical specification reference.
6-7-79 XVI 1
AP A-5 (6-8) - Rod Sequence Control System Malfunction - Revised technical specification reference.
6 79 XVI 2
AP A-6 (4-3) - RPT System A or 3 Trip - Revised in accordance with Plant Mod. 78-76.
6-7-79 XVI 1
' AP A-6 (6-7) - MSIV Pit Hi Te=p. - Revised in accordance with Plant Mod. 78 -127.
6-7-79 XVI 1
AP A-7 (3-5) - RPT System A or 3 Out of Service -
Revised in accordance with Plant Mod.78-127.
6 79 XVI 1
AP UA-2 (1-6) - Hydrogen in Generator Press.
Hi/Lo - Revised setpoint.
6-7-79 XVI 1
AP UA-5 (3-2) - Boiler No. 2 Drum Level Low Cutoff - Update procedure.
6-7-79 XVI 1
AP UA-5 (3 Degasifier Slower Trip - Add possible LCO condition and technical specification reference.
6-7-79 XVI 1
AP UA-5 (5-3) - Fuel Oil Storage Tank Level Low -
Update procedure and' technical specification reference.
6 79 XVI 1
AP UA-5 (3-6) - Diesel Gen. 3 Fuel Storage Tank Level Hi/Lo - Update procedure and technical specification reference.
6-7-79 XVI 2
AP UA-5 (6-2) - Boiler No. 2 Trouble - Add reduction of overall auxiliary " steam supply.
OPERATING MANUAL PROCEDURF. CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 6-7-79 XVI 1
AP UA-5 (6-3) - Fuel Oil Storage Tank Level High -
Update procedure.
6-7-79 XVI 1
AP UA-5 (1-1) - Boiler No. 1 Drum Level Hi -
Updates procedure.
6-7-79 XVI 1
AP UA-5 (1-2) - Boiler No. 2 Drum Level High -
Updates procedure.
6 79 XVI 1
AP UA-5 (2-1) - Boiler No. 2 Drum Level Low -
Updates procedure.
6 79 XVI 1
AP UA-5 (2-2) - Boiler No. 2 Drum Level Low -
Updates procedure.
6-7-79 XVI 1
AP UA-5 (3-1) - Boiler No. 1 Drum Level Low Cutoff - Updates procedure.
6-7-79 XVI 3
AP UA-5 (6-4) - Cire. Water Debris Filter -
Orgininal Issue.
6-7-79 kVI 1
AP UA-5 (6-6) - Diesel Gen. 4 Fuel Storage Tank Level H1/Lo - Update proceddre and technical specification reference.
6-7-79 X
5 PT 3.1.2.1 - Reactor Coolant kecirculation System - Revised to reflect te chnical specification requirements.
6-7-79 III 21 OP-24'- CAC System - Made editorial revisions.
6-7-79 III 13 OP Standby Gas Treatment System - Revised method of burping the drywell via-SBGT.
6-7-79 IV 46 GP General Plant Operating Procedure -
Update per NRC concerns.
6-7-79 III 22 OP Reactor Recirculation System - Revised sequence of o,peration to reduce crud buildup in pump seals and in accordar. e with recent plant modifications.
6 79 III 20 OP CAC System - Adds panel, terminal and valve numbers for jumper for CAC override switch which is no longer functional per Plant Mod.77-098.
6 EI-2.1 - Rupture Inside Drywell - Adds panel, 6-9-79 VI terminal and valve numbers for ju=per for CAC override switch which is no longer functional per Plant Mod.79-098.
OPERATING MANUAL P".dCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CllANGE 6-12-79 III 12 OP RCIC System - Corrects circuit number.
6-12-79 X
4 PT 25.2P - Seismic Monitor Triaxial Time History Accelographs - Revised key nu=ber.
6-12-79 X
0 PT 3.2.1P - RPT System Reactor Hi Pressu:
Trip Channel Functional Test - Original issue.
6-12-79 X
2 PT 14.4 - Control Rod Drive Eousing Support Inspection - Revised to be in compliance with Section 7.1.2 of Volume I.
6-12-79 X
6 PT 41.1 - Reactor Building Crane - Adds sign-of f blocks and overall upgrade of procedure.
6-12-79 X
2 PT 41.2 - Inspection of Crane Hooks, Crane Brakes, Ropes and Chains - Add sign-of f for Shif t Foreman and computer update.
6 79 I
4 PT 19.7 - Reactor Building, Turbine Scilding, and RER SW Booster Pu=p Motor Heat Exchang,ers -
. Deleted use of teflon tape and revised and added.
sign-of f blocks.
6-12-79 X
8 PT 19.4 - Safety / Relief Valve Pressure Test -
Correctad reference and revised and added sign-oir.
6-12-79 XVI 3
AP A-4 (5-4) - Cleanup Leak Hi/Hi - Revised setpoint in i. cordance with Plant Mod.77-399.
6 79 XVI 1
AI' A-4 (4-4) - Cicanup Leak Ei - Revised setpoint in accordance with Plant Mod.77-399.
6 - 12
.'9 XVI 2
SI Maintenance and Testing of the Security System - Updated to reflect new equipment.
6-15-79 XI 6
QAP On-Site QA Surveillance - To define the Book I system for tracking surveillance reports.
6 79 IV 47 GP General Operating Procedure - Revises 2A-1 and 2A-2 sequence sheech for cycle 3 on Unit No.1 6 79 X
5 PT 35.1 - Fire Protection System - Revised wording on annunciator window referenced in the procedure.
6-20,79 X 2
PT 55.2PC - Reactor Pressure Loop Calibration,
Revised in accordance with Plant Mod.77-370.
6-20-79 X 2
PT 2.1.4PC - PCIS - Reactor Low Water Level 12 Channel & Functional Test - Adds switches for Reactor Pump Trip System.
OPERATINC !MNUAL PROCEDURE CllA?tCES REV.
DATE VOL.
NO.
NUMBER & TITLE /Cl!ANGE 6-25-79 XI 11 Book 2, Q-list - Added Table 1A, a lis t of Q-list instruments.
6-25-79 XX 2
ENP Cable Pull Slip Form Documentation -
Incorporated " original (in blue)" stamp on the cable pull slips. Changed the ti=e of filing pull slips to reduce the chance of misplacing them.
Removed the requirement of QA witnessing termination to QA approving the termination.
6-28-79 X
6 PT 19.6.1 - Safety-Related Snubber Functional Testing - Clarified instructions on functional testing and added data sheet.
6-28-79 X
4 PT 19.6.0.1 - Visual Inspection of Inaccessible Snubbers on Safety-Related Systems - Revised to add explicit instructions and to record additi;nal data.
6-2 3-79 X
3 PT 19.6,0.2 - Visual Inspection of Accessible Snubbers on Safety-Related Systems - Revised to
. add explicit instructions and to record additional information.
6 79 I
1 PT 60.1 - Six Inch Fuel Pool Cooling Check Valves - Revised to include all required signatures.
6 79 VIII 3
R,C&T 0101 - Calibration and Setpoint Determinatist for Main Steam Line Monitors - To =ake calibration frequencies consistent with revised technical specifications and to comply with IE Bulletin 79-08.
6-29-79 VIII O
RC&T 1320 - Calibration of Portable Conductivity Bridges - To develop an approved calibration procedure.
6 79 VIII O
RC&T 1300 - Standardization of pH Meters - To develop an approved method for standardization of pH ceters.
6 79 VIII 0
RC&T 4000 - For=at, Approvals and Revisions for RC&T Instructions and Procedures - To reflec: the new RC&T procedure numbering sequence and to change RC&T Procedure 2001 to 4000. Delete RC&T Procedure 0001.
6 79 VIII O
RC&T 200. - Radioactive Airborne Ef fluent Releases & Reports - To reflect new Environmental Tech. Spec. limits and to change RC&T Instruction 7021 to RC&T Procedure 2000.
Delete RC&T Instruction 7021.
OPERATT!!C MANUAL PROCEDURE CIIANCES REV.
DATE VOL.
NO.
NIDIBER & TITLE / CHAT *GE 6-29-79 VIII' 0
RC&T 1310 - Calibration of Spectrophotometers -
To develop a calibration procedure for spectrophotoceters.
6-29-79 KVII 6
Security SI Security Post Duties, Responsibilities and Patrol Procedures - To update the procedure due to changes to the Security system.
6 79 I
0 SK4 - Issuing of Materials and Tools - Procedure Book 4 for material and tool issue from the storeroom.
6 79 I
O SKS - Housekeeping - To control storeroom Book 4 housekeeping that can affect the quality of parts.
6 79 I
0 SK5 - Packaging of Q-list Items - To establish the Book 4 requirements for packaging Q-list items during shipping, handling and storage.
6-29-79 I
O SK7 - Shipping - To establish the reqd' re=ents for i
Book 4 loading and shipping Q-list items.
OPERATTUC !1ANUAL PROCEDLTtE C1!ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIL\\NGE 7-2-79 XII 3
MP Corrective Maintenance - To include the CP&L priority system and to make editorial changes.
7-2-79 X
7 PT 1.1. 7PC - Average Power Range Monitor - Fixed and Flow Biased (Thermal) Neutron Trips Channel Calibration - To change the flow biased upscale alarm setpoint change, to clarify the LPRM calibration procedure and to add clarification of equipment designations.
7-5-79 X
2 PT 1.5.3PC - Source Range Monitoring System Channel Calibration and Functional Test - To improve the calibration procedure, to correct data sheets and to add sign-of f s and inf ormation.
7-2-79 XVII 7
SI Security Communications - To implement the new Security system coc=unication changes.
7-6-79 III 14 OP Condensate and Feedwater - Changed Electrical and Valve Lineup Sheets.
7-6-79 III 3
OP-43 Chlorination Syr em - To update procedure, depressurize pipe and add sinimum chlorination concentration.
7-6-79 VI 0
EI Flood Level in RHR Room - This is the initial issue.
7-6-79 VI 0
EI-46.2 - Flood Level in RPCI Room - This is the initial issue.
7-6-79 VI O
EI-46.1 - Flood Level in Core Spray Room - This is the initial issue.
7-6-79 VIII 0
RC&T Procedure 3210 - Chlorine Sampling Instructions - To change RC&T Instruction 4363 to RC&T Procedure 3210.
7-6-79 VIII O
RC&T Procedure 3211 - Amperometric Titration Method for Total Free Chlorine - To change RC&T Instruction 4364 to RC&T Procedure 3211.
7-6-79 VIII 0
RC&T Procedure 3230 - Operating Instructions for Chlorination System - To change RC&T Instruction 4365 to RC&T Procedure 3230.
7 7.9 I
5 PT 55.3PC - Reactor Vessel Level Loop Calibrations - Changed the valving-in and valving-out of the transmitter.
7-6-79 VIII 0
RC&T Procedure 3270 - Temperature Monitoring -
To change RCST Instruction 4366 to RC&T Procedure 3270.
OPERATTNG 11ANUAL PROCEDURE CllANCES REV.
DATE VOL.
NO.
ERDER & TITLE /C1 LANCE 7-6-79 VIII 0
RCST Procedure 1130 - Determination of Sodium Pentaborate Solution in Standby Liquid Control Tank - To :hange RCST Instruction 4025 to RC&T Procedure 1130.
7-6-79 VIII O
RC&T Procedure 3240 - Glass Electrode Method for pH Determination - To change RC&T Instruction 4131 to RC&T Procedure 3240.
7 79 VIII 0
RC&T Procedure lill-Chloride Ion by Mercuric Nitrate Titration - To change RC&T Instruction 4032 to RC&T Procedure 1111 and to make minor technical changes.
7-6-79 VIII O
RC&T Procedure 1110 - Chloride Deter =ination by Color - To change RC&T Instruction 4030 to RC&T Procedure 1110 and to make minor technical changes.
7-6-79 VIII 0
RC&T Procedure 1120 - Conductivity Measurements -
To change RC&T Instruction 4045 to RC&T Procedure 1120 and to make minor technical changes.
7-6-79 VIII O
RC&T Procedure 1141 - Water and Sediment in Crude 011 - To change RC&T Instruction 4204 to RC&T Procedure 1141.
7-6-79 VIII 0
RC&T Procedure 1200 - Radioactive Liquid Waste Analysis - To change RC&T Instruction 5502 to RC&T Procedure 1200.
7-6-79 VIII 0
RC&T Procedure 1211 - Analysis for Radiciodine in Charcoal Cartridges and Filters - To change RC&T Instruction 5507 to RCST Procedure 1211.
7-6-79 X
5 PT 2.1.9PC - RCIC Isolation Instrumentation -
Steam Leak Detection System Channel Calibration and Functional Test - Revised to verify the valve lineup at completion of PT.
Removed the note on calibration sign-of f section.
7 79 X
2 PT 2.1.12PC - RCIC Stead Line High Differential Pressure Channel Calibration and Fun:.ti Jnal Test -
Revised to verify the valve lineup at completion o f PT.'
Removed the note in calibration sign-of f section.
7-6-72 X
12 PT 2.1.9P - RCIC Isolation Instrumentation - Steam Leak Detection System - Revised to verify the valve lineup at the completion of the PT.
OPERATIUC !!ANUAL PROCEDURE C1fANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /C11A"GE 7-6-79 X
1 PT 2.10.9PC - RCIC. Isolation Instrumentation -
Steam Leak Detection System Channel Calibration and Functional Test - Revised to verify the valve lineup at the co=pletion of the PT.
7-6-79 2
Special Procedure 79 Inspection and Testing Procedure for Concrete Anchors - Added the inspection of 2h" and s= aller pipe.
7-6-79 III 25 OP Reactor Water Cleanup - Added to the lis t of valves to be closed.
7 79 XVI 1
Unit No. 1 - A-4, 5 Annunciator Procedure -
Revised to comply with Plant Modification 78-284.
7-6-79 XVI O
Unit No. 1 - A-4, 6 Annunciator Procedure -
New annunciator added by Plant Modification 77-85.
7 79 XVI 0
Unit No. 1 - A-4, 5 Annunciator Procedure -
New annunciator added by Plant Modification 77-85.
7-6-79 XVI 0
Unit No. 1 - A-4, 3 Annunciator Procedure -
New annunciator added by Plant Modification 77-85.
7 79 XVI 0
Unit No. 1 - A-4, 4 Annunciator Procedure -
New annunciator added by Plant Modification 77-85.
7-6-79 XVI 2
Unic No. 1 - A-5,.1 Annunciator Procedure -
Changed action step 7 to bypass and deleted jumper.
7-6-79 XVI 1
Unit No. 2 - A-5, 1 Annunciator Procedure -
Changed action step 7 to bypass and deleted j umper.
7-6-79 X
2 PT 2.1.5PC - RC&T Turbine Steam Line Low Pressure Calibration and Channel Functional Test - Added valve lineup verification at completion of PT and removed note on calibration sign-off section.
7 79 X
21 PT 2.1.12P - RCIC Steam Line High Differential Pressure Channel Functional Test - Added valve lineup verification at completion of PT.
7-6-79 X
15 PT 2.1.5P - RCIC Turbine Steam Line Low Pressure Channel Functional Test - Added valve lineup verification at co=pletion of PT.
7-6-79 X
5 PT 1.1.12PC - High Steam Line Radiation Channel Calibration and Functional Test - Updated alarm /
trip setpoints and corrected data sheet numbering.
OPERAT7NC MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-6-79 X
10 PT 2.1.8FC - RCIC Turbine Exhaust Diaphragm Righ Pressure Channel Functional Test - Added valve lineup verification at co=pletion of PT.
7-6-79 I
2 AI Plant Tool Administration - Deleted -
Book 2 Superceded by SK-4 in Volu=e I, Book 4.
7-6-79 III 9
OP-32.1 - Condensate Deep Bed Deminerali:er System - Corrected typographical error.
7-6-79 III 0
OP Torus Drain Keep Fill System - To incorporate Plant Modifications77-255 (Unit Sa 1)
AND 77-256 (Unit No. 2) into the OP.
7 79 I
0 SK Material Requisition and Reorder Procedures Bxnc 4 and Responsibilities - New revision to comply with ANSI require =ents.
7 79 I
O SK Receiving - New procedure to comply with
~
Ebck 4 ANSI requirements.
7-12-79 I
0 SK Storage - New procedure to comply with Book 4 ANSI requirements.
7-12-79 I
O SK Randling - New procedure to comply with Book 4 ANSI requirements.
7-12-79 I
O TI-501 - Storekeeper Training - New procedure to 3xnt 3 provide a training program for training and certifying storekeepers as receipt inspectors and fork lif t operators.
7 79 I
17 AI Material, Requisitions, Receiving and Badc 1 Storage - Deleted entire instruction and incorporated in Storekeeper instructions.
7-13-79 I
12 AI Collection, Maintenance, Control and 3xnc2 Storage of Plant Records - Consolidated AI-2 and AI-2.1 to inc.lude controls for master copies of tech. =anuals, IS0s, and plant drawings and defined method of making changes to closed QA records.
Added cleanliness requirements to Permanent Storage Vaulb 4ef',ned records classified as contro11ec and noncentrolled and referenced fire protection procedure for vaults.
7 79 I
4 AI-2.1 - Control of Drawings, Specifications, &
Back2 Document Control - Delete instruction to be incorporated in.AI-2.
7-13-79 IV 6
CG Guideline for Preparation of Operations Work Procedures - To update procedure.
OPERATINC 14ANUAL PROCEDURE Cl!ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /Cl!ANGE 7-13-79 X
11 PT 2.2.1 - Pri=ary Containment Isolation System -
Add E41-F042 to valve cycling list.
Added as Step 38.
Make closing time 80 seconds.
7-17-79 3
Special Procedure 79 Inspection and Testing Procedure for Concrete Expansion Anchors - Field check of torque / tension correlation required changes in torque valves.
7-17-79 X
1 PT 19.6.3 - Inspection of Safety-Ralated Snubbers Which Have Experienced an Unusual Shock - Added Shift Forenan sign-off and made same revisions
=ade in pts 19.6.0.1 and 19.6.0.2.
7-17-79 X
3 PT 41.2 - Inspection of Crane Hooks, Crane Brakes, Ropes and Chains - Added additional cranes and revised data form.
7-17-79 X
10 PT 2.1.7P - HPCI Turbine Exhaust Diaphragn High Pressure Channel Functional Test - Adced steps and valve lineup checkoff sheets.
7-17-79 X
1 PT 2.1.7PC - HPCI Turbine Exhaust Diaphragm High Pressure Channel Calibration and Functional Test -
Added steps and valve lineup checkoff sheets and removed note on calibration sign-of f.
7-17-79 X
12 PT 2.1.3P - EPCI Steam Leak Detection System -
Added a step to isolate the CO2 system. Added steps and valve lineup checkoff sheets.
7-17-79 X
1 PT 2.18FC - RCIC Turbine Exhaust Diaphragm High Pressure Channel Calibration and Functional Test -
Added steps and valve lineup checkoff sheets.
Revised terminals to show the dif ference between Unit No. 1 and Unit No. 2.
7-17-79 X
15 PT 2.1.2P - EPCI Turbine Steam Line Low Pressure Channel Functional Test - Added steps and valve lineup checkoff sheets, added blank to fill in date of last calibration and revised valve position.
7-17-79 X
14 PT 2.1.1P - HPCI Steam High D/P Channel Functional Test - Added steps and valve lineup checkoff sheets and added high and low water tank valves.
7-17-79 X
1 PT 2.1.lPC - EPCI Steam High Differential Pressure Channel Calibration and Functional Test - Added steps and valve lineup checkoff sheets and deleted the note on calibration. sign-off.
OPERATING MMiUAL PROCEDURE C11ANCES REV.
DATE VOL.
NO.
NIADER & TITLE /Cl!N;GE 7-23-79 I
29 Book 1 - Adainistrative Procedures - Updated the text and figures.
7-23-79 VI 2
EI 20 - Main Steam Line Leaks - Updated the
=anual actions.
7-23-79 VI 7
EI 1.2 - Rupture Inside Drywell - Revised to provide operator guidance on resetting the ADS timer.
7-23-79 VI 5
EI 5.1 - Loss of Pri=ary Contain=ent (Normal Operation) - Updated " Symptoms" and " Manual Actions".
7-2 3-79 SP 3
SP 79 Inspection and Testing Procedure for Concrete Expansion Anchors - A field check of torque / tension correlation required minor changes in the test and reinstallation.
7 79 VI 5
EI 4.2 - Moderator Temperature Decrease - General update of these emergency instructions.
7-23-79 VI 4'
EI 6 - High Pressure Coolant Injection Failure-Corrected ADS logic and ensured CS and LPCI su=ps running before ADS is used manually.
7-23-79 VI 6
,EI 15.1 - Station Blackout operation - Added nuclear service water pu=p auto start to the automatic actions.
7-2 3-79 VI 5
EI 16 - Main Condenser Tube Failure - Ravised to eliminate redundant actions.
7-23-79 VI 2
EI 5.2 - Loss of Primary Containment (Accident Conditions) - General update of the procedure.
7-2 3-79 VI 1
EI 42 - Turbine 3uilding Closed Cooling Water System Failure - General update of the procedure.
7-2 3-79 VI 4
EI 15.2 - Degraded Auxiliary Electrical Pcwer Operation - General update of the procedure.
7-23-79 VI 2
EI 4.7 - Improper Startup of Idle Recirculation Pump - General update of the procedure.
7-23-79 XVI 2
Unit No. 2, UA-2,1 Hydrogen in Generator Pressure Hi/Lo - Changed alarm setpoint f rom 43 psi to 50 psi.
7 79 X
4 PT 45.3.3 - E=crgency Core Cooling System (ECCS) -
Added information, corrected typographical errors, split PT into two. parts and added points created by Plant Modification 78-266.
OPERATING ffANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NmmER & TITLE / CHANCE 7-2 3-79 X
6 PT 2.1.3PC - HPCI Isolating Instrumentation -
Added steps and valve lineup checkoff sheets to verify valve lineup at completion of PT.
Removed note on calibration sign-of f sheets. Added sign-off for isolation of RPCI CO2 system.
7-23-79 X
2 PT 3.1.11PC - Emergency Core Cooling System -
Added steps and valve lineup checkoff sheets to verify valve lineup at completion of PT.
Re=oved note on calibration sign-off section.
7-2 3-79 X
1 PT 2.1.2PC - ECCS - HPCI Turbine Steam Line Low Pressure Calibration and Channel Functional Test -
Added steps and valve lineup at PT completion.
Removed note on calibration sign-off.
Added test gauge information on calibration
- and valve position informatien.
7-2 3-79 X
13 PT 3.1. ll? - ECCS - Suppre'ssion Chamber Righ k'ater Level Channel Functional Test - Added ' steps and valve lineup check-off sheets to verify valve lineup at PT completion.
7-23-79 X
2 PT 45.2.13 - PCIS (Croup 4) - EPCI Steam Line Low Pressure Response Time.Added test points due to plant modifications, changed recorder chart speed, added gauge calibration info and added steps and valve lineup checkoff sheets to verify the valve lineup at FT completion.
7-23-79 XII O
MP Control of Measuring Devices and Test Equipment - Made editorial changes and changes to meet new QA and NRC requirements.
7-23-79 SP 1
SP 79 Recirculation Pu=p Trip Test - Added X marks in approp'riate blocks as required for periodic test.
7-23-79 III 14 OP Control Rod Drive System - Corrected valve lineup and added a precaution that will help to minimize rod select switch problems resulting from overheating.
7-25-79 XX 0
ENP Licensee Event Reports (LERs) - Initial issue of this procedure.
7-31-79 I
4 TI-200 - Brunswick Plant Operating Retraining Book 3 Program - Clarified " classroom training," proviid a means of evaluating licensed personnel and corrected errors on assigned responsibilities.
OPERATING ffANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 7-31-79 I
13 AI Plant Filing Instructions - Added new Bode 2 index titles and revised periods of retention of strip charts.
7-31-79 III 7
OP Diesel Generator - Corrected PRV nu=bers.
7-31-79 X
1 PT 45.3.4 - ECCS - EPCI Initiation Response Ti=e -
Added infor=ation and equipment required to perform the test.
Added steps and valve lineup checkof f sheets to verify valve lineup at test completion.
7-3 1-79 X
11 PT 7.1.9 - Core Spray Si=ulated Automatic Actuation and Logic Functional Test - Added gauge calibration date, changed sequences of starting the pumps and opening valves and added steps and valve lineups following PT complecion.
7-31-79 X
1 PT 15.1 - Standby Gas Treatment System Filter Test - Added steps to verify ths system is returned to operable status and to ensure proper review of associated special procedure.
7-31-79 X
2 PT 15.3 - SBGT Charcoal Canister Absorption Test -
Deleted this PT; now perfor=ed by.PT 15.1/
7-31-79 X
1
,PT 15.2.2 - SBGT Charcoal Leak Test - Deleted this PT; now performed by PT 15.1.
7-31-79 X
1 PT 15.2.1 - SBGT HEPA Ef ficiency Test - Delted this PT; now performed by PT 15.1 7-31-79 X
2 PT 35.17 - Fire ;ctection System - Revised to reflect changes made by the fire protection modifications.
7-31-79 X
2 PT 45.2.14 - PCIS (Group 4) - HPCI Steam Line High Differential Pressure Response Time - Added steps and valye lineup checkoff sheets and added test jacks installed by plant modifications.
7 79 X
3 PT 3.1.2PC - ECCS - Concensate Storage Tank Low Water Level Channel Calibration and Functional Test - Added steps and valve lineup checkoff sheets and removed a note on calibration sign-off sheets.
7 79 X
10 PT 3.1.2P - Core Standb'y Cooling System Test and Checks - Added steps and valve lineup checkof f sheets.
7-31-79 X
1 PT 56.lPC - ECCS RER and Core, Spray System Pu=p Pu=p Start Ti=a Delay Relays Calibration -
Corrected typographical error.
OPERATTMC !!ANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NU10ER & TITLE / CHANCE 8-1-79 XIX 0
FP General Fire Plan for Permanent Storage Vault - Initial issue of a procedure for the actions to take during a fire.
8-1-79 XII 3
MP Maintenance Procedure - Added a policy for handling material during f abrication or repairs, clarified responsibilities given in MP-25 and MP-30, changed QA responsibilities on investigating equipment failures and updated reference for ordering parts.
8'3-79 I
1 SK Storekeeper Instruction-Storage - Added Book 4 the details of the rodent control program.
3-3-79 IVII 7
SI Security Instructions - Records, Re po r ts,
Inspections and Audit Procedures' - Added revisions to i=plement the new security modifications.
8-3-79 X
7 PT 46.1 - Locked Valves - Added a note that CW valves V33-40 are applicable to Unit No. 1.
The Unit No. 2 debris filter modification deleted these valves.
8 79 IV 48 GP General Plant Operating Procedure -
Revised to clarify stesps and responsibilities.
8-3-79 SP O
SP 79 Prepared Source Holders for Shipment and for Handling and Loading the Shipping Cask -
This is the initial issue of this procedure.
8-3-79 VI 1
EI Flood Level in RRR Room - Updated and clarified the procedure.
8 79 VI 1
EI-46.1 - Flood Level in Core Spray Room -
Updated and clarified the procedure.
8-3-79 VI 1
EI 46.2 - Flood Level in EPCI Room - Updated and clarified the. procedure.
8-8-79 XX 7
ENP Q-List Modification Control - Added a s tatement that the bases of why a plant modification does not involve an unreviewed safety question or technical specification change is required on the Safety Analysis.
8-13-79 X
2 PT 35.3 - HPCI Carbon Dioxide Flooding System -
Revised to include flow testing and to update the entire procedure.
3-13-79 SP 4
SP 79 Inspection and Testing Procedure for Cencrete Expansion Anchors - Added the acceptance criteria for anchor installations and reinstall-ation information for new vedge anchors.
OPERATT!!C MANUAL PPOCEDURE CHANCES REV.
DATE VOL.
NO.
NU1 DER & TITLE /CHANGC 8 79 X
4 PT 45.3.5 - ECCS-L?CI Initiation Response Time -
~
Added valve lineup sheets, listed cables, defined electrical and pressure switches, added notes which specify which section to perform and added figures to aid to setting up.
8 79 x
6 PT 55.3FC - Reactor Vessel Level Loop Calibrziens-Revised to incorporate plant modification changes to the instrument piping.
8 79 XVII 1
SI Emergency Plan Support - Revf. sed to incorporate the modified security system.
8-16-79 X
0 PT 55.' - Re=ote Shutdown RHR Head Spray Flow Calibration - Initial issue of this calibration PT.
8-16-79 X
0 PT 55.8 - Remote Shutdown RHR System Flow Calibration - Initial issue of this calibration PT.
8-16-79 X
0 PT 55.9 - Rmote Shutdown RHR Service Water j
Discharge D/P Calibration - Initial issue of this calibration PT.
3-22-79 VII 2
MP General Welding Procedure - Procedure updated to correct minor errors to provide more information and better coordination.
3-22-79 I
1 AI Spent Fuel Shipping Cask Interf ace Document - Incorporated the latest Brunswick and Robinson interf ace document for cask maintenance.
3-22-79 X
2 PT 2.1.26PC - PCIS - Main Steam Line Low Pressure Channel Calibration and Functional Test -
Corrected typographical errors and removed a note on calibration sign-off sheets.
8 79 X
9 PT 8.1.2 - LPCI - Simulated Automatic Actuatien and Logic Functional Test - Added steps for calibration, added infor=ation, moved the pump test steps and added steps to check valve positions.
S-22-79 X
4 PT 1.1.9PC - Average Power Range Mcnitor-Flow Units - Changed N012C to N014C.
3-22-79 XIX 1
FP Fire Suppression System Valve Control -
Incorporated the fire protection modifications.
8 79 X
15 PT 3.1.5P - Emergency Core Cooling Sysr.es -
Revised to install jumpers during testing.
OPERATING MANUAL PROCEDURE CIIANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CitANCE 8-22-79 X
5 PT 1.5PC - RBM - Control Rod k'ithdrawl Block Channel Calibration and Functional Test -
Corrected typographical error.
8-22-79 XX 8
ENP Q-list Modification Procedure - Added a fire hazard analysis and a Return on Invest =ent (ROI) analysis.
8-22-79 X
14 PT 40.2.5 - Turbine Control Valve Testing -
Revised to test control valves at reduced power.
Referenced the =argin to the rod block line as well as the load line.
8-22-79 X
4 PT 40.2.2 - Auto =atic Pu=p Starts - Deleted note and steps not required, added information and revised to clarify.
8 79 III 10 OP-32 Condensate Deep Bed Deminerali:er System - Added a precaution step following maintenance on the system.
8-22-79 III 7
OP-32 Condensate Filter Demineralizer System -
Added a precaution step foll'owing =aintenance on the system.
8-22-79 IV 49 CP General Plant Operating Procedure - Added a precaution step following maintenance on the condenser, revised and deleted info to update.
8-22-79 III 3
OP DC Electrici System - Added a new section to provide instructions for looking for D.C.
grounds.
8-22-79 X
2 PT 36.4A - Stator Cooling - Corrected typograph-ical errors, clarified steps and listed annunciators expected.
8-22-79 X
10 PT 4.1.1 - Process Radiation Monitors-Reactor Building Vent. Exhaust Monitoring System - Revised to conform to plant conditions (...all available supply and exhaust fans running).
8-22-79 X
14 PT 10.2 - RCIC - Revised to conform with PT 10.1.1.
8-22-79 X
12 PT 2.2.1 - Pri=ary Contain;ent Isolation System -
PCIS Valves - Updated to. incorporate Plant Modification 77-256 and added Shif t Foreman sign-offs.
8-22-79 X
2 PT 37.2.2 - Reactor Feedpump Turbine Stop Valve Test - Revised to conform to Operations pts.
OPERATT!!C !!M3UAL P!tCCEDURE C1!ANCES REV.
DATE VOL.
NO.
NtDGER & TITLE / CHANGE 8-22-79 X
4 PT 40.2.6 - Turbine Overspeed Trip Test - Ravised to conform to Operations pts.
8-22-79 X
3 PT 37.2.1 - Reactor Feedpu=p Turbine Governor and Trip Mechanism Tcsc - Revised to conform to Operations pts.
8-22-79 X
5 PT.33.2 - Testing Standby EHC Pump - Revised to conform to Operations pts.
8-22-79 X
3 PT 33.1 - EHC Accumulator Precharge - Revised to confor= to Operations PT..
8-22-79 X
4 PT 34.1 - Auxiliary Bciler System - Revised to conform to Operations pts.
~
8-22-79 X
4 PT 37.2.3 - Reactor Feedpu=p Turbine Thrust Bearing Wear Test - Revised to conform to Operations pts.
3-22-79 X
4 PT 36.1 - Stator Cooling System - Revised to conform to Operations pts.
8-22-79 X
3 PT 37.1 - Reactor Feedpump Turbine Overspeed Check - Revised to cenfor= to Operations pts.
8-22-79 III 22 CP Containment Atmospheric Control System -
Revised to prevent inadvertent opening of CAC valves.
8 79 XI 7
QAP On-Site QA Surveillance - Revised to Book 1 clarify information required in the response to surveillance reports.
8 79 X
3 PT 1.1.1PC - RPS - Reactor High Pressure Trip Channel Calibration & Functional Test - Added jumpers to PCIS instrumentation to reduce the possibility of reference leg scra=s and removed a note on calibration sign-of f sheets.
8-30-79 X
7 PT 55.3PC - Reactor Vessel Level Loop Calibrations - Added ju=pers to reduce the possibility of reference leg scrams.
8-30-79 XII 3
MP Qualification of Weld Procedure Specifications and Welders - Revised to comply with ASME codes and QA Surveillance Report #539.
S-30-f9 X
4 PT 19.6.0.2 - Visual Inspection of Accessible Snubbers on Safety-Related Systems - Revised to allow functional testing of snubbers found low on fluid and to clarify steps.
OPERATTf!C f tNIUAL PROCEDURE C1!MICES REV.
DATE VOL.
NO.
NU} DER 6 TITLE /Cl!A: ICE 8-30-79 X
1 PT 3.2.1P - Recirculation Pu=p Trip System -
Jumpers added to RPS instruments to reduce the possibility of scrams.
8-31-79 X
5 PT 19.6.0.1 - Visual Inspection of Inaccessible Snubbers on Safety-Related Systa=s - Revised to allow functional testing of snubbers with low fluid to prove operability and to clarify steps.
O O
OPERATTUC !!ANUAL PROCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /C11ANCE 9-4-79 0
SP 79 Fire Protection-Underground Pipe Flushing Procedure - New procedure to be issued to detail the flushing requirements for the underground fire protection piping.
9-4-79 VI 3
EI-37.1 - Operations During Hurricane Warnings and Hurricane Conditions - Revised method of securing cranes, the preparation of the diesel generators and typographical errors.
9 79 I
1 AI-9.2 - Identifying and I=plementing Required Book 2 Changes to Technical Specifications - Updated the entire procedure, changed the procedure title and added forms to aid in making and tracking Technical Specification changes.
9-13-79 X
10 PT 3.1.14P - ECCS - Reactor Low Pressure Channel Functional Test - Added electrical jumpers to the RPS and PCIS logic to reduce the possibility of a reactor scram. Divided the procedure 'into two sections with reactor pressure determining which section is to be performed.
Disabled the pressure switch annunciators when the pressure is less than 500 psig.
9 79 X
3 PT 55.2PC - Remote Shutdown Reactor Pressure Loop Calibration - Added electrical jumpers to the RPS logic to reduce the possibility of a reactor scram Added blank for the date of the last calibration of test gauges.
9-13-79 X
15 PT 1.1.1P - Reactor Protection Test - Reactor High Pressure Trip Channel Functional Test -
Added an electrical jumper to the PCIS instrument to reduce the possibility of reactor scrams.
Added a blank for the date of the last test gauge calibration.
9-13-79 X
4 PT 3.1.5PC TCCS - Reactor Vessel Shroud Level Channel Calibration - Added an electrical jumper to the RPS instruments to reduce the possibility of a reactor scram.
Removed a note from the data sheets since the colu=n must be fillied in anytime calibrations are done.
9-13-79 X
2 PT 17.11P - Spare Plant Batteries - Deleted spare cell #398 from the data sheet since the cell was installed in a plant battery.
9-13-79 X
6 PT 24.2 - Containment Atmospheric Monitoring System Component Test - Revised to correct an error in the penetration nu= bering.
OPERATI!!C ENUAL PRCCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9 79 XX 9
ENP Q-List Modification Procedure - Revised to require that the fire hazard analysis be performed by the fire protection system engineer.
Deleted the requirement for drawings to list all applicable codes, specifications, procedures and special. requirements. Added budget information and made editorial changes.
9 79 I
1 TI-301 - Storekeeper Training - Added length of Book 3 time certification exists before renewal and added company name to certification sheets.
9 79 III 23 OP Reactor Recirculation System - Revised to allow more margin on the APRM scram setpoint when restarting a reactor coolant recirculation pump during power operation. Added a section for recovery from pu=p runback or scoop tube lockout.
Updated the procedure.
9-14-79 III 7
OP Fire Protection System - To in' corporate new syste=s installed as part of fire protection modifications.
9-14-79 III 15 OP Condensate and Feedwater - Revised per LER 2-79-22 corrective action. LER recorted high reactor vessel conductivity due to excessive
, condenser tube leakage.
9-14-79 X
11 PT 8.2.4 - RER Service Water System Component Test - Revised to add new baseline data due to pump =aintenance.
9-14-79 XVI 10 PT 8.1.3 - LPCI/RER System Component Test -
Added the LER corrective action and simpliff ed the data sheet.
9-14-79 X
13 PT 14.1 - Control Rod Operability Check - Revised to agree with other operations test initial conditions.
9-17-79 VI 2
EI Power Range Neutron Monitoring System Fallare - Updated the Technical Specification reference.
9 79 VI 9
EI Reactor Scram' - Updated the Technical Specification reference.
9-17-79 VI
' 2' EI Condensate and Feedwater Failure - Updated the Technical Sp.ecification reference.
9 79 N/A 1
SP-79 Fire Protection - Underground Pipe Flushing Procedure.- Added addit,1onal valves to the valve lineup.
OPERATING MANUAL PROCEDUitR CilANCES REV.
DATE VOL.
NO.
NUIDER & TITLE /CIL\\NGE 9 79 N/A 0
SP 79 Operating Procedure for Chem-Nuclear Radwaste Solidification - New procedure to incorporate the Chem-Nuclear solidification process.
9 79 X
24 PT 3.1. 7P - ECCS - Reactor Low Water Level #2 and
- 3 Channel Functional Test - Revised to jumper PCIS instrumentation while performing the test.
Added steps to connect and disconnect a V0M.
9 79 X
8 PT 1.1. 7PC - APRM - Fixed and Flow 3iased (Ther=al) Neutron Trips Channel Calibration -
Added tolerances and clarifications.
9-19-79 X
6 PT 35.1 - Fire Protection System - Revised to incorporate plant modifications.
9-19-79 IV 50 GP General Plant Operating Procedure - Added A-1 rod sequence checkout sheets for Unit No. 1 for cycle 2.
9 79 X
1 PT 35.12.4 - Recirculation Motor - Generator Sets Deluge Systems - Revised procedure to make more efficient. Added thermal sensors.
9 79 X
15 PT 9.2 - HPCI System Component Test - Added caution note concerning duty cycle on D.C.
Limitorque valves.
9-19-79 X
9 PT 10.1.1 - RCIC - Flow Rates at 1000 PSIG -
Added caution note concerning Limitorque valves duty cycle.
9 79 XVI 1
UA-28, 3 SW Intake Structure Flood Level High Annunciator Procedure
'.a=pletely updated the procedure.
9-19-79 XVI 1
UA-1, 4 Deep Bed Pressure Differential High -
Deleted a redundant annunciator per Plant Modification 79-60.
9-19-79 II 5
FH PWR Fuel Handling Operations - Added the Engineering Supervisor to the procedure sign-off sheet. Specified that SRO and the bridge operator =ust verify PWR fuel cove =ent and provided a sign-off sheet for them.
9-19-79 III 4
OP Lube Oil Storage and Conditioning System -
Revised the order of the shutdown procedure.
9 79 VI 6
EI-4.5 - Recirculation Flow Control Failure -
Decreasing Flow Changed corresponding to nulled.
OPERATTUC IIANUAL PROCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIIANCE 9 79 VIII 1
RC&T 2000 - Radioactive Airborne Effluent Releases and Reports - Revised cubic feet to CFM and effluent to efficiency.
9-19-79 X
5 PT 40.2.2 - Automatic Pump Starts - Revised to conform to Operations' pts.
9 79 X
15 PT.40.2.5 - Turbine Control valve Testing -
Revised to conform to Operations' pts.
9 79 X
3 PT 16.2 - Primary Containter.t Volumetric Average Te=perature - Revised to conform to Operations' pts.
9 79 X
2 PT 27.1 - H, Seal Oil System - Revised to conform to Operations' pts.
9-19 -79 III 20 OP Residual Heat Removal System - Added a caution note concerning the Limitorque valve's duty cycle.
9 79 III 19 0P Eigh Pressure Coolant Injection System Added a caution note concerning the Limitorque valve's duty cycle.
9-10-79 III 13 OP RCIC System - Added a caution note concerning the Limitorque valve's duty cycle.
9-19-79 X
8 PT 1.10 - SRM and IRM De".ection Position Rod Block Functional Test - Revised to conform to Operations' pts.
9-19-79 X
10 PT 1.6.2 - Rod Worth Minimizer System - Revised to conform to Operations' pts.
9-19-79 X
15 PT 10.2 - RCIC - Added a caution note concerning the Limitorque valve's duty cycle.
9-19-79 XVI 1
UA-1, 2 Filter Demineralizer Pressure Differential High - Deleted this redundant annunciator.
9 79 XVI 1
UA-1, 5 Filter Demineralizer Exhausted Flow Conductivity - Deleted this redundant annunciator.
9-19-79 XVI 1
UA-1, 5 Deep Bed Demineralizer System Treuble -
Deleted this redundant manunciator by Plant Modification 79-60.
9-19-79 XVI 1
UA-1, 3 Filter Demineralizer System Trouble -
Deleted this redundant annunciator.
9-19-79 XVI 1
UA-1, 5 Deep Bed Exhaused Flov. Conductivity -
l Deleted this redundant annunciator.
OPERATING !!ANUAL PROCEDURE CIIANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9 79 VIII O
RC&T 0111 - Routine /Special Survey for Removable Surface Contamination - Added new instru=entation, added daily smear survey and changed from RCST Instruction 7004 to RC&T Procedure 0111.
9 79 VIII O
RC&T 0100 - Routine /Special Dose Rate Survey -
Added new instrumen:ation, removed smear surveys and changed from RCST Instruction 7003 to RC&T Procedure 0100, 9-19-79 VIII O
RC&T 0110 - Monitoring Personnel for Contamination -
Added precautions against spreading contamination, added new instrumentation and changed f rom RC&T Instruction 7002 to RC&T Procedure 0110.
9-19-79 VIII.
O RC&T 0120 - Routine /Special Airborne Radioactivity Survey - Added new instrumentation, added additional steps for surveying and changed RC&T Instruction 7005 to RC&T Procedure 0120.
9 79 VIII 0
RC&T 0420 - Whole Body Counting - Changed RC&T Instruction 7007 to RC&T Procedure 042d.
9 79 VIII 0
RC&T 0400 - Investigation of Lost or Damaged Personnel Dos 1=etry Devices and Overexposures -
Added reporting requirements and changed from RC&T Instruction 7009 to RC&T Procedure 0400.
9 79 VIII O
RCST 0230 - Issue and Use of Radiation Work Per=it - Revised procedure and changed from RCST Instruction 7010 to RC&T Procedure 0230.
9-19-79 VIII O
RC&T 0211 - Use and Wearing of Protective Clothing - Changed frco RC&T Instruction 7027.
9 79 VIII O
RCST 0210 - Personnel De' contamination - Changed from RC&T Instruction 7012.
9-19-79 VIII O
RC&T 0003 - Action to be Taken if Equip =ent Does Not Meet Required Criteria - Changed from RC&T Instruction 7030.
9-19-79 VIII O
RCST 3260 - Temperature Rise and Canal Level Review - Changed from RCST Instruction 8509.
9 79 VIII O
RC&T 3000 - Sa=pling and Analysis Schedule for Envir.on= ental Technical Specification Items -
Revised the procedure reference nu=bers and changed from RC&T Procedure 0006.
9 79 X
10 PT 4.1.8 - Of f-Gas Hi Rad Operability Check -
Revised to conform to Operations' pts.
OPERATTUC MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 9-19-79 X
3 PT 5.2 - Su=p Pu=ps/ Coolers Operability Test -
Revised to conform to Operations' pts.
9 79 X
6 PT 15.6 - Standby Gas Treat =ent Operability -
Revised to conform to Operations' pts.
9 79 X
6 PT 23.1 - Control Building IVAC Systems - Revised to conform to Operations' Pi s.
9-19 -79 X
2 PT 15.4A - Secondary Conta!.n=ent' Integrity -
Revised to conform to Operations' pts.
9-19-79 X
4 PT 18.2 - Service Platform Interlock Check -
Revised to conform to Operations' pts.
9-19-79 X
4 PT 12.2.1 - ECCS D/G Logic Test - Revised to conform to Operations' pts.
9 79 X
5 PT 1.1.6 - Reactor Protection Instrument Check -
Revised to conf orm to Operations' pts.'
9 79 X
11 PT 9.3 - HPCI 165 PSIG Flow Test - Added a caution note concerning the ' duty cycle of Limitorque valves.
9-19-79 X
7 PT 15.4 - Secondary Containment Integrity (SBGT) -
Revised to conform to Operations' pts.
9-2 1-79 XVII 7
SI Security Pos t Duties, Responsibilities, and Patrol Procedures - Reduced the frequency of E-Field and microwave testing on Security.
9-21-79 I
1 SK Material Requisition and Reorder Procedures Bodc 4 and Responsibilities - Added a distribution list for Q-list purchase orders.
9-21-79 XIX 1
FP Fire Protection Procedure - Revised to include the fire plans distribution requirements.
9-21-79 XII 13 MP Calibration of Process Instruments -
Revised to incorporate the Corporate QA Manual's latest revision.
9-21-79 XII 3
MP Writing Corrective Maintenance Instructions Revised to incorporate the latest revision of the Corporate QA Manual.
9-21-79 XII 10 MP Preventive Maintenance Program - Revised to incorporate the latest revision of the Corporate QA Manual.
9-24-79 I
0 AI-10.1 - Receiving the Spent Fuel Shipping Cask -
Back 2 This is the initial issue of this procedure.
OPERATING MANUAL PROCEDURE C1!ANCES
~
REV.
DATE VOL.
NO.
NUMBER & TITLE /C11ANGE 9-27-79 X
1 PT 1.9E - Axial Alignment of Traversing Incore Probes - Deleted calibration of TIP amplifier which is perfor=ed in PT 1.9D.
9-27-79 X
3 PT 35.2 - Fire Protection System - Added a new fire hydrant.
9-2 7-79 X
4 PT.12. 2 d - No. 4 D/G Monthly Load Test - Revised to conform to Operations' pts.
Added the request to the Shif t Foreman to perform thia PT.
9s27-79 VI 9
EI-1.2 - Rupture Inside Drywell - Updated entire procedure inclusing GE SIL on Yarway level indication and note on MSIV limit switches in LOCA conditions.
9-27-79 VI 4
EI Abnormal Reactor Water Levels - Revised to include the GE SIL on Yarway level indication and the change to low level #3.
9-27-79 VI 11 EI-1.1 - Primary System Rupture Inside,Drywell (Leaks) - Revised to include GE SIL on Yarway level indication and note on MSIV limit switches in LOCA condition.
9 79 VI 10 EI Reactor Scram - Revised to include GE SIL on Yarway level indication and note on MSIV li=it switches in LOCA condition.
9-27-79 VI 3
EI-5.2' - Loss of Primary Containment - Revised to include GE SIL on Yarway level indication and note on MSIV limit switches in LOCA conditions.
9-27-79 III 20 OP EPCI System - Added information from GE SIL on Yarway level indication.
9-27-79 III 10 OP Circulating Water Systems - Added information on MSIV limit switches in LOCA condition.
9-27-79 X
3 PT 50.5 - Total Core Flow Calibration - Revised to include a new computer generated core flow calculation.
9-27-79 N/A 1
UA-3,1 De=ineralized Water Storage Tank Level High/ Low - Revised. the setpoints.
9-27-79 X
10 PT 9.5 - 1000 PSIG Flow Rate Test - Added a caution on the duty cycle for D.C. LAmitorque valves.
9-27-79 X
8 PT 10.1.3 - RCIC. Flow Rates at 150 PSIG -
Added a caution on the duty cycle for D.C.
Limitorque valves.
OPERATTUG MANUAL PROCEDURE C1tANCES REV.
DATE VOL.
NO.
NU}mER & TITLE / CHANGE 9-2 7-79 IV 11 OG Radioactive Gaseous Release Control -
Revised to delete quarterly average limit paragraph, changed the base values on 10 day and 30 day reports and made a general update.
9-27-79 X
4 PT 12.2c - No. 3 D/C Monthly Load Test - Added a request to the Shif t Foreman before performing this test.
9 79 X
4 PT 12.2b - No. 2 D/G Menthly Load Test - Added a request to the Shift Foreman before performing this test.
9-27-79 X
4 PT 12.2a - No. 1 D/G Monthly Load Test - Added a request to the Shif t Foreman before performing this test.
9-27-79 X
3 PT 35.17 - Fire Detection System - Revised to prevent actuation of the area deluge valves.
9-2 7-79 IV 51 GP General Plant Operating Procedure - Added precautions to avoid of f-gas spiking due to centrol rod double-notching above 60% core flow.
9-27-79 VI 6
EI-4.1 - MSIV Closure - Added a note on MSIV limit switchet in LOCA conditions.
9-27-79 X-6
'PT 9.3a - EPCI System Component Test - Revised the table for allowable ranges of test quantities to eliminate confusion.
9-27-79 N/A 1
UA-3, 2 SJAU Steam Pressure High Pressure Regulator Valve Trouble - Revised the setpoint due to a plant =odification.
9-2 7-79 N/A 1
UA-3, 3 SJAE Steam Pressure Low - Revised the setpoint due to a plant modification.
9-27-79 IV 3
OG Unit No. 2 and Unit No. 1 Separetion Procedure - Delete the entire procedure since it is no longer required.
9-2 7-79 III 14 OP RCIC System - Added information f rom GE SIL on Yarway level indication.
9-28-79 X
6 PT 10.1. la - RCIC Sys tem Component Test - Revised the valve lineup to change the pump suction from the CST to the torus.
9-2 3-79 X
0 PT 48.0 - Public Address (Page and Party Line)
System - Initial procedure issue.
9-28-79 III 23 OP Containment Atmosphe ric ' Control System -
Deleted an item that no longer applies due to a modificart-a.
OPERATTUC MANUAL PROCEDURE CHANCES REV.
DATE VOL.
50.
NUMBER & TITLE / CHANGE 9-23-79 X
3 PT 1.5.3PC - SRM Sys tem Channel Calibration and Functional Test - Corrected typographical error, clarified the acceptance criteria and corrected the data sheets.
9-28-79 X
I PT 56.4?C - Reactor Vessel Level Loop Calibration - Revised to jumper. PCIS and RPS instrumentation and to remove the note from the data sheets since the infor=ation is required anytime instruments are checked.
9-23-79 XVII 3
SI Industrial Security Alerts - Updated the telephone nu=bers.
9-28-79 XVII 5
SI Surveillance Require =ents and Procedures -
Revised to specify when the guards can use their weapons.
9-28-79 XVII 6
SI Civil Disturbances O Revised to delete the use of shotguns during civil disturbances.
9-28-79 X
2, PT 45.1.5 - RPS-MSIV Closure Circuit Response Time - Updated, added reference sheet, revised to perform at power and increased chart speed.
9-28-79 X
B PT 1.1.12PC - High Steamline Radiation Channel
, Calibration and Functional Test - Added hold points to perform source calibration.
9-2 8-79 X
3 PT 45.1.2 - RPS - Reactor Low Water Level #1 Response Time - Updated, reduced chart speed and clarified a note on testing cycles.
9-28-79 X
0 PT 26. lP - Seismic Monitoring System - Initial issue of this triaxial time-history accelerographs channel functional test, i
8
OPERATTMC MANUAL PROCEDURE CHANCES
~
REV.
DATE VOL.
NO.
NWBER & TITLE /CllANGE 10 79 VI 5
EI High Pressure Coolant Injection Failure -
Revised low level #3 to -105.0"; co=pletely updated and included GE SIL 289.
10 79 I
13 AI Collection, Maintenance, Control and Bk.2 Storage of Plant Records - Revised to add instru-ctions for handling aperture cards, to provide accountability for notification of plant =odifi-cation i=plementation and to establish the criteria for the control of Confidential Documents, 10'5-79 X
5 PT-35.5 - Fire Extinguisher Service and Inspection
- Revised to include portable fire extinguishers.
10 79 X
1 PT-35.ll.1 - Hose Rack Inspection - Added new hose racks and ' updated the hose type listing.
10 79 XX 0
ENP Engineering Evaluation for Temporary Repairs - Initial procedure issue.
10-9-79 VI 5
EI-15.2 - Degraded Auxiliary Power - Revised to
. update the ninimum switchyard voltage for all
=otors during LOCA conditions.
10 79 X
3 PT-6.2.1 - SLC Relief Valve Test - Revised to a more restrictive frequency due to instru=ent drif t 10-9-79 III 8
OP Fire Proection System - Revised to ensure all required areas were supplied with a water supply.
10-12-75 I
2 AI-9.1 - Identifying and Implementing Required Bk.2 Changes to Technical Specifications. Revised the safety analysis to delete "or any changes to the Technical Specifications required".
10 75 X
0 PT-35.18.2 - Swinging Fire Doors - To ensure operability of swinging fire doors via periodic inspection and reduce expense by quick repair of needed items.
10-15-75 X 1
PT-35.14 - Inspection of' Self-contained Breathing Apparatus - To include all air paks and include additional testing requirements.
10-17-75 X 6
PT-33.2 - Testing Standby EHC Pu=p - Revised to delete reference to the pump discharge filters indicator which is ne longer installed.
10-17-7! I 3
TI-300 - General Employee Training - Revised to Sk.3 bring up-to-date.
Added training on clearance procedure and respiratory protegtion equipment.
OPERATING ffANUAL PROCEDURE CllANCES l
REV.
DATE VOL.
50.
NUMBER & TITLE /CIIANGE 10- 2 3-79 XII 3
MP General Welding Procedure. - Revised to provide a procedure for documenting welding on Class II-A and non-Q piping; to provide a proce-dure for use of the "FYRITE" oxygen analyzer and to delete the weld " cut card".
10 75 X
1 PT-3.1.14PC - ECCS - Reactor Low Pressure Channel Calibration and Functional Test'- Added jumpers to RPS and PCIS logic to reduce possibility of scrams and steps to lif t wires from switches not being testing (when shut down). Deleted a note from the Data Sheets.
10-2 3-79 X-2 PT-3.1.7PC - ECCS - Reactor Low Water Level #2 and
- 3 Channel Calibration and Functional Test -
Revised to jumper PCIS instrumentation while per-forming PT to reduce the possibility of a scram.
02anged Switches 1 and 2 settings due to Plant Modification 79-216.
10-23-75 X
0 PT-46.3PC - Control Building Chlorine Detection Sys tem Calibration - New calibration PT as re-quired by standardized Technical Specifications.
10- 2 3-75 X
4 PT-45.1.4 - RPS-APRM Neutron Flux-High (15% and 120%) - Corrected cabinet designation, terninal designation and spelling.
10 - 2 3-75 X
2 PT-45.1.6 - RPS - Turbine Stop Valve-Closure Circuit Response Time - Revised to allow testing in the "run" = ode. Revised to add tes t jacks added by Plant Mod 77-306 and 78-266.
10-23-75 X
1 PT-1.1.14PC - RPS MG Set Channel Calibration -
Revised to switch between the normal and alternate supplies, to lif t wires to the MG set windings and to calibrate the underfrequency relay using a different procedure.
10-23-75 X
5 PT-9.1 - HPCI Simulated Automatic Actuation and Logic Functional Test - Added a reportability statement and various panel numbers, changed jumper removal instructions and corrected a typo.
10 -2 4-75 VI 0
EI Resin Injection into the Reactor Vessel -
Initial issue of this procedure.
~
10 7C III 26 OP Reactor Water Cleanup - Revised to incor-porate the knowledge gained from a Unit i scram due to resin infection into the reactor vessel.
~
10 75 X
0 PT-35.12.3 - Standby Gas Treatment Train Deluge System - Initial issue of this procedure.
OPERATTMC f tANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIL\\NGE 10-25,-75 N/A 5
SP-79 Inspection and Testing Procedure for Concrete Expansion Anchors - Added Data Sheet and expanded the section on anchor bolt installation.
10-25-75 VI 3
EI Main Steam Line High Radiation - Revised co supply instructions to the 3perators for the operation of MSIVs.
10-25-75 III 9
OP Service Water System - Revised to incor-porate a procedure to flush the RER SW piping af ter use.
10-25-75 X
3 PT-1.2.4A - APRM Inop. - Updated to clarify and to ensure the minimum number of operable channels are met.
10 75 X
12 PT-8.2.4 - RER Service Water System Component Test
- Corrected dP vs flow graph.
10-25-75 I
2 SK !aterial Requisitica and Reorder Procedures Bk.4 and Responsibilities - Added QA to the Blanket Q-list procedure, changed routing requirement and specified that an engineering evaluation can be perfor=ed when QA requirements cannot be deter-mined.
10 75 I
14
,AI Plant Filing Instructions - Updated filing Bk.2 categories, added new filing numbers and retention ti=es and clarified retention times.
10-25-75 III 2
MI-25 Welding Instruction P-88-B Editorial changes made.
10-25-75 XII 2
MI-25 Welding Ins truction P-1-1-B Editorial changes made.
10-25-75 XII 2
MI-25 Welding Instruction P-8-8-B Editorial changes made.
10-25-75 XII 1
MI-25 Welding Ins truction F-8-8-BA Editorial changes made.
10-25-79 XII 2
MI-25 Welding Instruction F-1-8-BA Editorial changes made.
10 75 XII 1
MI-25 Welding Ins truction P-8-8-BA Editorial changes made.
10 75 XII 1
MI-25 Welding Instruction F-8-(17-4PH)-A-8 Editorial changes made.
10 79 XII 1
MI-25 Welding Ins truction P.-1-1-SW Revised to comply with MP-25, Revision 3.
OPERATING MANUAL P!!OCEDURE CIIANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /CIIANCE 10 75 XII 1
MI-25 Welding Instruction P-34-34-3-1
- Editorial changes made.
10 75 XII 1
MI-25 Welding Ins truction P-45-(CARP.20)-
P-45-(CARP.20)-B Editorial changes =ade.
10-25-75 XII 1
MI-25 Welding Ins truction F-8-(17-4PH)-A-9
- Editorial changes sade.
10-25-75 XII 1
MI-25 Welding Instruction P-34-CA958-B-S -
Editorial changes made.
10-25-79 XII 0
MI-25 Welding Ins truction F-1-1-BA Initial issue of this procedure.
10-25-75 XII-0 MI-25 Welding Ins truction F-5-5-A Initial issue of this procedure.
10-25-79 XII 1
MI-10-506A - Crane Che=pu=ps - Updated and added procedure signoffs.
10 79 XII 1
MI-16-523 - Vertical Inline Pu=ps Series No. 3180
- Cleanup Backwash Transfer Pu=p - Revised to comply with MP-16.
10 79 XII I
MI-16-536 - Main Steam Isolation Valves - Revised
,to comply with MP-16 and Corporate QA requirements 10-25-79 X
1 PT-1.13 - LPRM Vibration Monitoring - Revised to meet ANSI N18.7 - 19 76.
10-25-79 XII 1
MI-3-3A10 - G31-PSH-N014 Static 0-Ring Pressure Switch, Model SN-AA3-TT - Revised to meet new CQA and NRC requirements.
10 79 XII 1
MI-3-3A18 - E51-PS-N009A&B Barksdale Pressure Switch - Revised to =eet new CQA and NRC requirements.
~
10-25-79 XII 1
MI-3-3A21 - E41-PS-N017A&B - Barksdale Pressure Switch - Revised to meet new CQA and NRC require =en ts.
10 79 XII 1
MI-3-3A22 - E41-PS' -N011A,B,C&D Barksdale Pressure d
Switch - Revd. sed to meet new CQA and NRC requirements.
10 79 XII
'l MI-3-3A29 - C71/C72-PS-5003A-D Barksdale Pressure Switch - Revised.co =eet new CQA and NRC requirements.
10-25-79 XII 0
MI-3-3A33 - 321-PIS-N0213 & N021D Reactor Low Pressure - Initial issue of this procedure.
OPERATTUC MANUAL PROCEDtmE CHANCES REV.
DATE VOL.
NO.
NmlBER & TITLE / CHANGE 10 75 XII O
MI-3-3B5 - E21-dPIS-N004A&B - Barton Pressure Indicator Switch - Initial issue of procedure.
10 75 XII 0
MI-3-4Cl - CO-CR Chloride Intrusion Monitor Calibration - Initial issue of this procedure.
10-25 -75 XII 1
MI-3-3H1 - Fenwal Temperature Switches - Revised to meet new CQA and NRC requirements.
10-25-75 XII 1
MI-3-3IA - Scram Discharge Volume Righ Water Level
- Revised to meet new CQA and NRC requirements.
t 10 75 XII 1
MI-3-3I3 - Magnetrol Flow Switch - Revised to =eet new CQA and NRC requirements.
10-25-75 XII-1 MI-3-3IC - Magnetrol Flow Switch - Revised to meet new CQA and NRC requirements.
10-25-75 XII 0
MI-3-3ID - Robertshaw Levtl Switch - Initial issue 10 75 XII 0
MI-3-4D1 - Post Accident Containment Pressure
- Initial issue of this procedure.
10 75 XII O
MI-3-4Q1 - Honeywell Model III Recorder - Initial
. issue of this procedure.
10 75 XII O
XI-3-451 - Containment Radiation Mcnitors -
Initial issue of this procedure.
MI-3-4' 2 - Oxygen / Hydrogen Recorder - It ial 10 75 XII 0
S issue of dais procedure.
10-25-75 XII 1
MI-3-6G1 - Flew Transmitter - Foxboro Model 99V
- Revised to meet new CQA and NRC requirements.
10 75 XII 0
MI-3-8D1 - Delphi Hydrogen Analyzer - Initial issue of this procedure.
10 7C XII O
MI-3-8El - Drywell H, Concentration - Initial issue of this procedure.
10 75 XII O
MI-3-BF1 - Drywell 0 Co'ncentration - Initial 2
issue of this procedure.
10-25-75 XII 0
MI-3-15I-l - Rod Block Monitors A&B - Initial issue of this procedure.
10- 25, 75 XII O
MI-3-15I Average Power Range Monitor-Flow Units - Initial issue of this procedure.
10-25-75 XII O
MI-3-15I Local Power Range Group Channel C _ibration
~nitial issue of this procedure.
OPERATTNG MANUAL PROCEDURE C11ANCES REV.
DATE VOL.
S0.
NUMBER & TITLE /CIIANGC 10-25-79 XII O
MI-3-15I Average Power Range Monitor - Fixed and Flow Biased (Thermal) Neutron Trips Channel Calibration - Initial issue of this procedure.
10-25-79 XII 0
MI-3-15S - Containment Radiation Monitors -
Initial issue of this procedure.
10-25-79 XII O
MI-3-22A - G16-FT-N003 - GEMAC D/P Transmitter Type 555 - Initial issue of this procedure.
10 79 XII 0
MI-3-223 - G16-FT-N013 - GEMAC D/P Transmitter Type 555 - Initial issue of this procedure.
10-25-79 XII O
MI-1 Heise Test Gauge (Pressure only) -
Revised to conform to MP-1, to incorporate the use of weight tables and to incorporate linearity and hysteresis checks.
10 79 XII 4
MI-1 Ashcrof't Test Gauge Calibration (Pressure Only) - Revised the calibration interval and to conform to MP-1.
Added linearity and hysteresis checks.
10-25-79 XII 4
XI-1 Ashcrof t Vacuum Test Gauge Calibration
- Revised to conform to MP-1, changed calibration frequency and added additi'onal checks.
10-25-79 XII 7
'MI-1 Wallace and Tiernan Pneumatic Pressure Calibration - Revised to conform to MP-1.
10 79 XII L
MI-31 Termination of Electrical Cables and Internal Wiring - Revised to use a field copy of the Cable Termination Form.
10-25-79 XII O
MI-16-550 - CFD Filters - Initial issue.
10-25-79 XII 1
MI-16-537 - Motor Operated Valve Actuators -
Revised to comply with MP-16, Revision 3.
Added a drawing and_ referred to the drawing.
10-25-79 XII 1
MI-16-515 - Reactor Water Cleanup Pu=ps - Revised to co= ply with MP-16 and MP-12.
Added flushing of the pump seal cooling.
10-25-79 XII 1
MI-16-502 - CRD Hydraulic Pump Suction Filter Replacement - Revised to. conform with MP-16.
10-25-79 XII 1
MI-16-561 - Disassembly / Reassembly of RER Service Water Booster Pu=p - Revised to conform to MP-16, Revision 3.
10-25-79 XII 1
MI-3-1BT - Sensall. Transmitter. Revised to meet new CQA and RNC requirements.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /C11ANGE 10-25-79 XII 1
MI-3-3A7 - Static 0-Ring Pressure Switch -
Revised to meet new CQA and NRC requirements.
10 79 XII 1
MI-3-3A8 - CRD Pu=p Permissive - Revised to meet new CQA and NRC requirements.
10-25-75 XII 1
MI-3-3All - E51-PS-N006 - Static 0-Ring - Revised to meet new CQA and NRC requirements.
10 79 XII 1
MI-3-3A15 - E51-PS-N020 - Barksdale Pressure Switch - Revised to =eet new CQA and NRC requirements.
10 75 XII 1
MI-3-3A16 - E51-PS-N030 - Barksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-7E XII 1
MI-3-3A17 - E51-PS-N019 A-D - Barksdale Pressure Switch - Revised'to meet new CQA and NRC
~
requiremen ts.
10 75 XII 1
MI-3-3A19 - E51-PS-N012A-D - Barksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-75 XII i
MI-3-3A20 - E41-PS-N027 - Barksdale Pressure
. Switch - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-3A24 - C21-PS-N007A&B - Barksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-75 XII 1
MI-3-3B4 - E51-dPIS-N017 & N018 Barton MDL-288
- Revised to =eet new CQA and NRC requirements.
10 75 XII 1
MI-3-3B3 - E41-dPIS-N004 & N005 Barton MDL-288
- Revised to meet new CQA and NRC requirements.
10 75 XII 1
MI-3-3B2 - Barton Model 288 - Revised to meet new CQA and NRC requirements.
10-25-75 XII 1
MI-3-3A25 - Ell-PS-N022A&B - Barksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10 75 XII 1
MI-3 *3A26 - Ell-PS-N016 A-D - 3arksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-7(
XII 1
MI-3-3A30 - EHC-PSL-1756 through 1759 - Revised to meet new CQA and NRC requirements.
4 CllA:lCES Of'El:AT f lC ?!A!!!IA.T. l'HCCI:D,ill:!:- _ _ _
REV.
DATE VD!_.
!:0.
NUiDER 6 TITLE /Citx:f:c 10-25-79 XII 0
MI-3-1AFl - Drywell 0, and H, Transmitters -
Initial issue of this~ procedure.
10 79 XII 0
MI-3-1AH1 - Fisher Level Transmitter - Initial issue of this procedure.
10-25-79 XII O
M1-3-2L3 - International Ins truments - Initial issue of this procedure.
10 79 XII 0
MI-3-2N -
Post Accident Pressure Indicator
~
Initial issue of this procedure.
10-25-79 XII 1
MI-3-3Al - Barksdale Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-3A2. Static 0-Ring Pressure Switch - Revised to meet new CQA and NRC requirements.
1 0 79 XII 1
MI-3-3A3 - Static 0-Ring Pressure Switch - Revised to meet new CQA and NRC requirements.
10-25-75 XII 0
.MI-3-3A31 - Barksdale Pressure Switch - Initial issue of this procedure.
10-25-75 XII 0
MI-3-1ALL - Intake Canal Level Transmitter -
Initial issue of this procedure.
10-25-75 XII 1
MI-3-LAK1 - GE Level Transsitter - Revised to meet new CQA and NRC require =ents.
10 75 XII 1
MI-3-1BR - Action PAK 4100 - Temperature Trans-
=itter - Revised to =eet new CQA and NRC require-men ts.
10 75 XII 1
MI-3-1BS - Sensall Transmitter - Revised to meet new CQA and NRC requirements.
10-25-75 XII O
MI-3-1BX1 - Rosemount Pressure Transmitter -
Initial issue of this procedure.
10 75 XII O
MI-3-1BX2 - Rosemount Pressure Transmitter -
Initial issue of this procedure.
10-25-75 XII 1
MI-3-lG1 - Bailey Level Transmitter - Revised to meet new CQA and NRC requirements.
10-25-75 XII 1
MI-3-1H1 - Bailey Pressure Transmitter - Revised tc meet new CQA and NRC requirements.
10 75 XII 1
MI-3-lH2 - Baile'y Pressure Transmitter - Revised to meet new CQA and NRC requirements.
10-25-7c XII 1
.MI-3-lH3 - Bailey Pressure Transmitter - Revised to meet new CQA and NRC requirements.
t 4
OPERATTUC MANUAL PROCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 10 79 XII 1
MI-3-lH4 - Bailey Pressure Transmitter - Revised to meet new CQA.and NRC requirements.
10 79 XII 1
MI-3-lHS - Bailey Pressure Transmitter - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-lPl - Yarway Level Switch - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-1P3 - Yarway Level Switch - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-lP2 - Yarway Level Switch - Revised to meet new CQA and NRC requirements.
10-25-79 XII 1
MI-3-2B2 - Yarway Secondary Indicator - Revised to meet new CQA and NRC requirements.
10-25-79 XII O
MI-3-2L1 - International Instruments Pressure Indication - Enitial issue of this procedure.
10 79 XII O
MI-S-2L2 - International Instruments Indicator
- Initial issue of this procedure.
10-25-79 XII 0
MI'-3-3A32 - Barksdale Pressure Switch - Initial issue of this procedure.
10-25-79 XII 1
MI-3-3A4 - Static O-Ring Pressure Switch -
Revised to meet new CQA and NRC requirements.
10 79 XII 1
MI-3-3A6 - Reactor High Pressure - Revised to meet new CQA and NRC requirements.
10 79 XII 1
MI-3-3A9 - Static 0-Ring Pressure ' Switch -
Revised to teet new CQA and NRC requirements.
10-26-79 XIII 11 Emergency Plan - Revised to add new NRC regulation ;
and requit9.ments to comply with Reg. Guide 1.101, to better organize the plan and to update.
10- 30 -79 I
2 SK Storage - Revised to list materials not Bk.4 included in this storage procedure.
10 79 I
1 SK Receiving - Revised to list materials not Bk.4 included in this receiving procedure.
10 79 X
4 PT-35.7 - Sprinkler and Deluge Systems - Revised to incorporate new valves and to incorporate an ANSI standard format.
14-30 -79 I
30 Administrative Procedures - Updated, added Volu=e Bk.1 V, Plant Performance Procedures, revised the fre-quency of Plant Operating Manual review, revised the Plant Operating Manual revision form and added a notification orocedure when using NRC red rhene.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 10 79 XX 1
ENP Licensee Event Report - Revised to report ques tionable items.
10 79 X
7 PT-2.1.3PC - HPCI isolation Instrumentation -
Added extra precaution requiring Operations to place the HPCI CO, system under clearance prior to the technician' entering the room.
10 79 XII 3
MP-ll - Control of Relay and Overload Settings -
Revised to satisfy QA and NRC requirements and to include editing changes.
10-31-79 XII 1
MI-3-1A1 - 332-FT-N014A-D and N024A-D - Revised to satisfy QA and NRC requirements.
10- 3 1-79 X
11 PT-8.1.3 - LPCI/RER System Component Test -
Added the starting of A and B RER room coolers.
10 7E N/A 0
SP-79-33A - 24 H6ur Diesel Generator Load Tes t
~
- Original issue of this procedure.
10 79 N/A 0
SP-79-33B - 24 ' Hour Diesel Generator Load Test
- Original issue of this procedure.
10-31-79 N/A 0
SP-79-33C - 24 Hour Diesel Generator Load Test
- Original issue of this procedure.
10-31-79 N/A 0
'SP-79-33D - 24 Hour Diesel Generator Load Test
- Original issue of this procedure.
10-31-79 X
6 PT-7.1.8 - Core Spray System Co=ponent Test -
Added a verification of the operation of the core spray rool cooler.
10-31-79 XII 2
MI-10-2E - Main Generator Brushes - Revised to satisfy QA and NRC requirements.
10-31-79 XII 0
MI-16 4KV (ITE) and Testing Breaker Racking Instruction
_ Initial issue of this procedure.
10-31-79 XII 2
MI-10-3D - Oxygen Analyzer - Revised to satisfy QA and NRC requirements.
10 79 XII 2
MI-10-3B - Feed Gas Analyzers - Revised to satisfy QA and NRC requirements.
11-1-79 XI 12 Q-List - Revised to add a list of consumables Bk.2 and expendables to the Q-List.
~
11 79 XVII 9
SI Vehicular Traffic and Parking Control
- Revised to update the responsibilities of the security specialist in the area of designated vehicles.
OPERATING ffANUAL PROCEDURE C! LANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /C11ANCE 11-2-79 VIII 1
RC&T 4000 - Format, Approvals and Revisions for RC&T Instructions and Procedures - Revised to provide guidance for having instruction procedures in-hand while working in the field.
11-2-79 XI O
QAP Procedure for Assigning Hold Points to Bk.1 Weld Data Cards - Initial issue of procedure.
11-2-79 XI O
QAF Procedure for the Review of Purchase Bk.1 Requisitions and Q-List Material Inspection Reports - Initial issue of this procedure.
11-2-79 XI O
QAP-li - Tool and Equipment Calibration - Initial Bk.1 issue of this procedure.
11-2-79 XI O
QAP Visual Inspection - Added a purpose Bk.1 statement.
11 79 XI 1
QAP Magnetic Particle _ Examination Procedure Bk.ll
- Added a purposc statement.
11 79 XI 1
QAP Liquid Penetrant Examination Procedure Bk.1
- Added a purpose statement.
1 1 79 XI 0
QAP Walk-through Inspection Procedure -
Bk.1 Original issue of this procedure.
1 1 79 XI 0
QAP Establishing and Reviewing Hold Points -
Bk.1 Original issue of this procedure.
11-2-79 XI 0
QAP Review of Work Request and Authorization Bk.1 Form, Initial and Final - Original issue.
11-2-79 XX 1
ENP Procedure for Performing Core Bores Through Secondary Containment - Revised to meet the requirements of ANSI N18.7-19 76.
11-2-79 XVIII 4
PN Special Work Authorization - Revised to add ' cost control information to aid in tracking engineering ptojects.
11 79 XX 10 ENP Q-List Modification Procedure - Added cost control information and revised to meet the requirements of ANSI N18. 7-1976.
11-2-79 XX 1
ENP Specification Preparation - Revised to
=ee t the requirements of. ANSI N18. 7-19 76.
11-5-19 VIII 1
RC&T-1300 - Standardization of pH Meters - Revised to incorporate the present practices into the procedure.
11 79 VIII 1
RC&T-3240 - Glass Electrode Method for pH Determination - Revised to incorporate the present practices into the procedure.
OPERATTNC MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 11-7-79 I
31 Ad=inistrative Procedures - Revised to cover the 3k.1 organizational changes, to include engineering ins tructions to mee t ANSI N18. 7-19 76 requiremen ts for terporary revisions, to correct the controls for engineering tests and to add the calibration nonconformance action form.
11-7-79 XX 1
ENP Control of Engineering Procedures and Instructions - Deleted the procedure since Volume 1 of the Plant Operating Manual controls the issue and revision of plant procedures.
11-9-79 XI 8
QAP Site Surveillance Procedures - Deleted the requirements for monthly status reports on out-standing surveillance reports.
11-10-70 N /A-0 SP-79 Special Test Procedur^e - Issued to test the stability of the master feedwater controller when switching from 1 to 3 ele =ent control in manual and auto positions.
1 1 75 III 16 OP Condensate and Feedwater - Revised
' Section G on transf erring the RFPT mas ter control-ler from auto to manual to mininize possible transien ts. Added sections to transfer the mastet feedwater controller from manual to auto and to transfer from 3 to 1 element control, and vice versa, to minimize possible transients.
11 75 IV 52 GP General Operating Procedure - Added refer-rals to OP-32 when switching the = aster feedwater from manual to auto and when switching f rom auto to manual.
11 75 IX 6
FH PWR Fuel Handling Operations - Revised to provide a method for checking out the refueling bridge and PWR hoist prior to loading or unloading the cask.
11-14-75 III 11 OP Main Steam System - Revised to add a precaution on unqualified limit switches.
11-14-75 X 14 PT-14.1 - Control Rod Operability Check - Revised to insert a requirement for an initial instead of check mark to identify a responsible person if a question should arise.
11-14-75 X 11 PT-13.1 - Reactor Recire. Loops / Jet Pu=p Oper-ability - Revised to ensure the loop flow is within the curve limits.
11-14-75 X 7
PT-24.2 - Containment Atmosphere Monitoring System Component Test - Revised to indicate that valve stem movement cannot be verified.
OPERATTMC ?MNUAL PROCEDURE CilANCES REV.
DATE VOL.
NO.
NU>BER & TITLE /CllANGE 11-14-79 III 11 OP Circulating Water Systems - Revised to add the debris filter =odification to the valve and electrical lineups and corrected typos.
11-14-79 X
9 PT-10.1.3 - RCIC - Flow Rates at 150 PSIG -
Corrected the switch positions for F004 and F005.
il-l4-79 X
10 PT-10.1.1 - RCIC - Flow Rates at 1000 PSIG -
Corrected switch positions for F054, F004 & F005.
11-14-79 X
13 PT-2.1.3P - EPCI Isolation Instrumentation - Steam Leak Detection Sy: 2m. Added a f ront view to the relay layout and revised to require CO, sys tem
~
under clearance.
11-14-79 X
3 PT-45.1.3 - RPS - Reactor High Pressure Trip Response Time - Changed the figure and test points to agree with Plant Mods78-266, 280, and 281.
Added jumpers to reduce the possibility of refer-ence leg scra=s.
Revised to vent pressure to head tanks.
11-14-79 X
4 PT-45.2.1 - Main Steam Line Tunnel Temperature Switch Response Time - Added a new Figure 1 and references for plant mods, along with test jack information.
Increased dh'e chart speed, 11-14-79 XI.
5 MI-1 Simpson 260 Series Multimeter - Revised to meet new NRC and CQA requirements.
11-14-79 XII 2
MI-1 Field Standard Calibration Instruction for Telethermometer - Revised to meet new NRC and CQA requirements.
11-14-79 XII O
MI-1 Brooklyn Ther=ometer - Original issue.
11-14-79 XII 0
MI-3-1BW - Beckman RA-5 Solu =eter - Original issue,
11-14-79 XII O
MI-3-4T1 - B21-FR-R613, GE Recorder Type 531 -
Original issue of this procedure.
11 79 XII O
MI-3-4Z1 - 321-LR-615, GE Recorder Type 530 -
Original issue.
11-14-79 XII 0
MI-3-5G1 - Foxboro Indicating Controller -
Original issue of this procedure.
11-14-79 XII
'O MI-3-1BH1 - 321-IUIT-15, GE-GAM-RAY Turbidity Monitor - Original issue.
11-14-79 XII O
MI-3-lP4 - 321-LIS-N042A&B, Yarway Level Switch -
Original issue.
OPERATING MANUAL PROCEDURE CHANCES REV.
DATE VOL.
NO.
NUMBER & TITLE / CHANGE 11 75 XII O
MI-3-2L4 - CAC-LI-3342 - Original issue.
11-14-75 XII O
MI-3-3I4 - E41-LSH-N015A&B - Original issue.
11-14-75 XII 0
MI-3-6N2 - 2VA-FY-3359 Original issue.
11 75 XII O
MI-3-6 Z - 1 & 2 - VA-FY-335 6-1, 3 35 8-1, and 3357 Moore ADB Module - Original issue.
11-14-75 XII 0
MI-3-ilAI - CW-LRA-761, ACROMAG Current Alarm Relay - Original issue.
e 11-14-75 XII 1
MI-10-3E - A0G-HCR-106 - Revised to satisfy new NRC and CQA requirements.
MI-10-3C - A0G-02 -108, Oxygen Analyzer - Revised 1
11 75 XII-1 to satisfy new NRC and CQA requirements.
11-14-75 XII 1
MI-3-3B1 - 321-LIS-N017A, E, C&D - Revised to satisfy new NRC and CQA requirements. '
11 75 XII 1
MI-3-3A23 - E41-PS-N031 - Revised to satisfy new '
NRC and CQA requirements.
11'-14-75 XII 1
MI-3-8J CG-AT-4138 through 4142 - Revised to satisfy new NRC and CQA requirements.
11-14-75 XII 2
MI-10-lH - Hewett-Packard X-Y Recorder - Revised to satisfy new NRC and CQA requirements.
11 75 XII 2
MI-10-3F - A0G-RADI-103, Ratemeter/ Analyzer -
Revised to satisfy new NRC and CQA requirements, 11-14-79 N/A 0
SP-79 Deaerator Dissolved oxygen Performance
- Original issue.
L 1-21-79 X
11' PT-10.1.1 - RCIC-Flow Rates at 1000 PSIG -
Revised to clarify the taking of torus te=perature readings and c.o ensure Technical Specification limits are not exceeded, 11 79 X
16 PT-10.2 - RCIC-System Cobponent Test - Revised to clarify the taking of torus te=perature readings and to ensure Technical Specification limits are not exceeded.
L1-21-79 X
7 PT-33.2 - Testing Standby EHC Pu=p - Revised to eliminate duplication and to initial the EHC su=p level recording.
L1-21-79 X
10 PT-10.1. 3 - RCIC-Flow Rates at 150 PSIG - Revised to clarify the taking of torus te=perature readings and to ensure Technical Specification limits are not exceeded.
OPERATING MANUAL PROCEDURE C11ANCES REV.
DATE VOL.
NO.
NUMBER & TITLE /C1LWCE L1-21-79 X
11 PT-9.5 - HPCI-1000 PSIG Flow Rate Test - Revised to clarify the taking of torus temperature reading:
and to ensure Technical Specification li=its are not exceeded.
L 1-21-79 X
12 PT-9. 3 - HPCI-165 PSIG Flow Test - Revised to clarify the taking of torus temperature readings and to ensure Technical Specification limits are not exceeded.
L1-21-79 X
7 PT-10.1.1.a - RCIC-System Co=ponent Test - Revised to clarify the taking of torus te=perature readings and to ensure Technical Specification limits are not exceeded.
L 1 79 X
8 PT-9.3.a - HPCI-Sys tem Component Test - Revised to clarify the taking of torus temperature readings and to ensure Technical Specification limits are not exceeded.
L 1 79 X
5 PT.36.1 - Stator Cooling System - General update to correct typos and clarify the procedure.
L 1-21-79 X
16 PT-9.2 - HPCI-System Component Test - Revised to clarify the taking of torus temperatures and to ensure Technical Specification ~ 1imits are not exceeded.
L1 79 VI 11 EI Reactor Scram - Revised to incorporate NUREG 0578 relating to a loss of feedwater transient.
[1 79 VI 7
EI-15.1 - Station Blackout Operation - Revised to incorporate NUREG 0578 relating to a loss of feedwater transient.
L 1-21-79 X
14 PT-1.2.4 - APRM High Flux and Downscale Test -
Revised frequency to once per seven days, only in Condition 1.
L1-21-79 III 27 OP Reactor Water Cleanup - Revised to remove pH requirecents.
L 1 79 X
13 PT-8.2.4 - RHR Service Water System Component Test
- Revised to add new baseline data and to ensure the pipes are flushed with well water.
L 1-25-79 VI 0
EI Loss of UPS - Initial issue.
11-25-79 VI 6
EI-15.2 - Degraded Auxiliary Electrical Power Operation - Clarification to cover loss of RPS MG sets and reactor scram /GP-1 isolation described in FSAR 14. 3.4.4
OPEllATING !tANUAI. Pl!CCCDtitm Cl!ANCES REV.
DATE VOL.
NO.
NtRDER & TITLE /C1tANGE 11 79 XVI 1
UA-6, 6 Annunciator Procedure - Revised to clarify the procedure.
11-25-79 XVI 1
UA-6, 6 Annunciator Procedure - Revised to clarify the procedure, ll-25.- 79 XVI 1
UA-6, 6 Annunciator Procedure - Revised to clarify the procedure, 11 79 N/A 0
SP-79 Special Test Procedure - Initial issue of this procedure for the operational checkout of UPS.
The procedure incorporates the preoperational test and additional transient tests.
L 1-2 7-79 N/A 1
SP-79 Checkout of Uninterruptible Power Supply
- Clarified the acceptance test, deleted unneces-sary steps 'and added additional checks requested by the NRC.
11-27-79 VI 3
EI-13.1 - Station Blackout operation - Revised to include actions on loss of RPS or UPS.
11-27 19 XVI 2
UA-13, 2 Generator Field Overexcitation -
Revised to remove the assumption that a loss of excitation is inevitable when this alarm occurs and describes more appropriate,cperator action.
L 1-2 7-79 VI 1
EI Loss of UPS - Added instru=entation which is lost when UPS is lost and not regained. Added instructions to =onitor neutron ins trumentation during 'cooldewn if the reactor is shut down.
11-27-79 X
1 PT-35.4.6 - Fire Detection System - Revised to reflect installation of additional detectors.
L 1-27-79 X
0 PT-35.4.5 - Fire Detection - Revised to reflect installation of additional detectors.
L 1-2 7-79 X
1 PT-46.3PC - Chlorine Detection Sys tem Calibration
- Revised to nake this PT compatible with the installed equipment.
11 79 X
2 PT-35.4.4 - Fire Detecticn - Revised to reflect installation of additional detectors.
11-27-79 X
1 PT-35.4.3 - Fire Detection - Revised to reflect installation of additional detectors.
L 1-2 3-79 N/A 0
SP-79 Main Generator Auto / Manual Voltage Regulator Tes t - Ori.ginal issue of this procedure.
11-2S-79 X
6 PT-36.1 - Stator Cooling System - Clarified the calculatG:n for the filter differential pressure.
OPERATf MC MANUAI. P!!OCI:DlmM CllAI!CES REV.
DATC VO!..
50.
NINER & TITLE /Cl!.CGE 11-29-79 X
5 PT-1.1.9PC - APRM-Flow Units - Corrected DVM number, changed tolerance on noncritical meter and corrected 5 point calibration procedura on flow trans mit ter.
11 79 XI 1
QAP Walk-Through Inspection Procedure -
Bk.1 Revised the frequency of inspections.
11-29-79 XI 0
QAP Plant Modification Review Procedure -
Sk.1 Initial issue to provide QA/QC guidelines.
11-29-79 XII 9
MP Handling the IF-300 Cask - Revised to allow operation of drain valve, added reference to FH-13, corrected typos and updated, 11-29-79 III 10 OP Service Water System - Changed the power supplies for the B&D RER service water pumps.
11 79 X
8 PT-46.1 - Locked Valves - I.dentified drywell valves and added additional acceptance criteria.
L1-29-79 XII 0
MI-1-37C - Calibration of AMP PDIG Hydraulic
' Crimping Tool - Original issue.
11-29-79 XII O
MI-1-373 - Calibration of AMP PDIG Ratchet Crimping Tool - Original issue.
L1-29-79 XII O
MI-1-37A - Calibration of Electrical Wire and Cable Insulation / Jacket Stripping Tools - Original issue.
[1 79 XII 3
MI-il Basler Power Factor Relay - Revised to comply with NRC and OQA requirements.
L1-29-79 XII 1
MI-11 Westinghouse Transformer Differential Relays Types HU and H4 Revised to comply with NRC and OQA requirements.
L 1-29-79 XII 1
MI-ll GE Loss of Excitation Relay Checkout -
Revised to comply with NRC and OQA requirements.
L1-29-79 XII 1
MI-ll-20-GEbndervoltageRelayCheckout for Model NGVll - Revised to comply, with NRC and CQA requirements.
.1-29-79 XII 1
MI-11 GE High Speed Dif ferential Relay Check-out for Model 12CFD22B2A - Revised to comply with NRC and OQA requirements..
1-29-79 XII 1
MI-il ITE Voltage Balance Relay Checkout for Model ITE 60 - Revis*ed to comply with NRC and OQA requirements.
.1-29-79 XII 2
MI-ll GE Instantaneous Overcurrent Relay Model 12PJC21A - Revised to comply with NRC and OQA recuirements.
OPEltATTilC !!AtJUAI. P!t0CEDUl:P. CllANCES REV.
DATE VOL.
NO.
NUMBER 6 TITLE /CHA"GE 11-29-75 XII 1
MI-ll GE Instantaneous Voltage Relay Model 12PJV12B - Revised to comply with NRC and O'A
~
require ents.
11 75 XII 1
MI-11 GE Auxiliary Target and Seal-In Relay Model 12RAA14A - Revised to comply with NRC and OQA requirements.
11 75 XII 1
MI-ll GE Undervoltage Relay (DC) Model NGV
- Revised to comply with NiC and OQA requirements.
lir29-75 XII 1
MI-11 GE Machine Field Ground Relay Checkout for Model 12PJGilE - Revised to comply with NRC and OQA requirements.
11-29-75 XII 1
MI-il-ll ITE Ground Fault Relay Checkout for Model GR-5-- Revised to comply with NRC and OQA requirements.
11-29-75 XII 1
MI-il GE Temperature Relay Checkout for Model 12IRT51 - Revised to comply with NRC and OQA requirements, 11 75 X
1 PT-21.1.1 - Control Building E=ergency Filter REPA Filter Efficiency Test - Deleted and incorporated into PT-21.1.
11-29-75 X
1 PT-21.1.2 - Control Building E=ergency Filters Charcoal Leak Test - Deleted and incorporated into PT-21.1.
11-29-75 X
1 PT-21.1.3 - Control Building E=ergency Filters Charcoal Canister Adsorption Test - Deleted and incorporated into PT-21.1.
11 75 X
2 PT-21.1 - Control Building Emergency Filters -
Revised to verify that the system is returned to operable status and to ensure the proper review of asso'ciated special procedures, 11-29-75 II 2
SD Core Spray System - Revised setpoints per Plant Modifications79-215 and 79-216.
11-29-75 II 4
SD Automatic Blowdown System - Revised set-points per Plant Modifications79-215 and 79-216.
11 75 II 2
SD Residual Heat Removal Systam - Revised setpoints per Plant Modifications79-215 and 79-216.
11-29-7c XX 2
ENP-7 Engineering Procedure - LERs - Revised due to a change in the organization and commitments to NRC.
OPERATI!!C f tA:;tfA1. P!t0CI'.!]t!!:M CilA :GES REV.
DATC "0L.
S0.
NU?mER t, TITLE /CitA :CC 11 75 XII 1
MI-il GE Over and Undervoltage Relay Model 12LAV53K - Revised to co= ply with NRC and OQA requirements.
11-29-75 XII 1
MI-ll GE Balanced Current Relay Checkout for Model 12IJC513 - Revised to comply with NRC and OQA requirements.
11-29-75 XII 1
MI-ll GE Models PJC32K and PJC32F Ins tantane-ous Overcurrent Relay - Revised to comply with NRC and 0QA requirements.
11L29-75 XII 2
MI-11 GE Undervoltage Relay Checkout Model 12IAV54F - Revised to comply with NRC and OQA requirements.
11 79 X
2 PT-46.0 - Cold Shutdown Valve Operability Test
- Added N/A on the loss of power test for motor operated steas supply valves.
11 75 III 21 OP Residual Esat Removal System - Revised to flush RER SW piping af ter use with sea water.
11 75 III 9
OP Makeup Water Treatment ~ System - Updated the procedure..
11-29-75 VI 3
EI-23.1 - High Airborne Activity in the Drywell While Ventilating, or While Drywell is Open for Access - Added reference to the Emergency Plan for determining necessary notifications.
11 75 XII 2
MI-11 GE Overvoltage Relay Checkout for Model 12IAV51A and 12LAV51D - Revised to comply with NRC and OQA requirements.
11 75 XII 2
MI-11 GE Model 12IJCV51B Time Overcurrent with Voltage Restraint - Revised to comply with KRC and OQA requirements.
11-29-75 XII 2
MI-11 GE Overcurrent Relay Checkout for Types IAC51A, IAC53B, IAC573, IAC66A, IAC66C - Revised to comply with NRC and 0QA requirementa.
11 75 XII 2
MI-11 GE Overcurrent Differential Relay Check-out for Model 12 LAC 51N7A - Revised to comply with NRC and OQA requirements.
11-29-75 XII 4
MI-3-20C CW-IDSH-3492 - Revised to comply wit' NRC and OQA requirements.
11-29-75 XII 2
MI-3-6P1 - VA-FI'Q-3359 - Revised to comply wi'.a NRC and OQA requirements.
OPF.RATTUC ?!ANUAI. PitOCT.Dt!!:1: CllA!!CES T
REV.
DATE VOL.
- 0.
NinfBER 6 TITLE /CllA::GE 11 75 VI 3
El-23.2 - Righ Airborne Activity in the Reactor Building - Added reference to the Emergency Plan for determining necessary notifications.
11-29-75 VI 3
EI-23.3 - Righ Airborne Activity in Occupied Spaces - Added reference to the Emergency Plan for determining necessary notifications.
11 75 VI 3
EI-23.4 - High Radiation in Accessible Areas -
Added reference to.the E=ergency Plan for deter-mining necessary notifications.
11 75 VI 3
EI-23.5 - Liquid Radioactive Spills - Added reference to the Energency Plan for determining necessary notifications.
MI-3-6Y1'- Cire. Water RTD Calibration Computer 11-29-75 XII O
Points A1062 through A1069 - Original issue.
11-29-75 XII O
MI-3-6 :1 VA-FY-3359-1 Flav Converter -
Original issue of this procedure.
11 75 XII O
'MI-3-4Y1 - L&N ARM Recorder - Original issue.
- 11. 75 XII 0
MI-3-454 - L&N Speedecax 'M' Mark III Recorder, RS-CR-36 36 - Original issue of this procedure.
11-29-75 XII 0
MI-3-453 - L&N Speedonax 'M' Mark III Recorder, RS-CR-3824 - Criginal issue of this procedure.
11-29-7C XII 0
MI-3-4D2 - Bailey ' Go-Line' Decorder - Original issus of this procedure.
11 79 XII 0
MI-3-4C4 - LSN Speedomax Recorder Type 'H',
RS-AR-869 - Original issue of this procedure.
11-29-7c XII 0
MI-3-4C3 - Conductivity Multipoint Recorder Typo
'H' Models, RXS-CR-865, RS-CR-866. Original is sue 1 1 7' XII O
MI-3-4 AA1 - CAC-TR-778 Bristol Recorder -
Original issue of this procedure.
11-29-7' XII 0
MI-3-1AG1 VA-FT-3359' Flow Transmitter -
Original issue of this procedure.
11-29-T XII 0
MI-3-lY1 - VA-FT-3356, 335 7 and 3358 -
Original issue of this procedure.
XII 0
MI-3-2L5 - CAC-PI-2703-2, 2 704-1 and' 2 704-2 11 7
- Original issue of this procedure.
11-29-7o X 3
PT-45.2.3 - HPCI Steamline Tunnel Temperature -
Righ (Response Ti=ci - Revised to add test jacks per Plant Modifications78-266 and 78-280.
OPTItAT(UC ttANU[d. PunCCDUnn CIIANGES REV.
DAT-VOL.
N0.,
NLS.ER t, TITLE /Ci!ANC" 11 75 XII 0
MI-3-3B6 - EPCI Pu=p Discitarge H/L Flow Signal
- Original issue, 11-29-7S XII 4
MI-10-3A - NMC Radiation Monitor and Drywell Analyzer Systems - Revised to comply with NRC and 0QA requirements.
11-29-7S XII 1
MI-10-4A - Instrument Air Dryers - Revised to comply with NRC and 0QA requirements.
11 75 XII O
MI-16-549 - Split Body Valves - Original issue.
11129-75 XII O
MI-10-51LA - Mechanical Inspection and Lubrication of L1=itorque Operators Ins talled in Q-List Sys tems
- Original issue of this procedure.
11-29-75 XII O
MI-16-543 - Bettis Actuator Mod.
- Original isstte of this procedure.
11 79 XII 1
MP Maintenance Procedure - Revised to comply with ANSI and CQA requirements.
11-29-7E X
2
.PT-45.2.4 - Primary Containment Isolation System
- Revised test jack connections per Plant Modifi-i cations78-266 and 78-280.
11-29-7E X
3 PT-45.1.7 - Turbine Control Valve Fast Closure Response Tims - Revised test points per Plant Modifications78-266, 76-280 and 78-281, and increased the chart speed.
11-29-75 XII 1
MI-10-504A - Joy Air Compressor Piston Clearance Check and Valve Inspection - Revised to comply with MP-10 and to provide valve inspection.
11-29-75 X
2 PT-45.2.2 - Primary Containment Isolatien System
- Revised test jack connections per Plant Modifi-cations78-266 and 78-280, and added functional checkout af ter reinstallation of thermocouples, 11-29-79 XII 2
MI-10-504B - Instrument and Service Air Check Valve Inspection - Revised to comply with MP-10.
11-29-75 XII 2
MI-25 Welding Instruction F-1-1-B Revised to comply with MP-25.
11-29-79 XII 2
MI-25 Welding Ins truction P-l-1-A Revised to comply with MP-25.
11-29-79 XII 2
MI-25-1 Welding Instruction P-1-1-A Revised to comply with MP-25.
11-29-79 XII 1
MI-25 Welding, Ins truction F-1-1-3A-1
. Revised to comply with MP-25.
Ol'El AT_IMC 'tA :tTA!. I' :CCI:DIII:l' Gila::CES REV.
DATE VO!..
?:0.
NU"nCR & TITLE /ClfA!!GC 11 75 XII 2
>G-25 Welding Instruction F-5-8-A ~
Revised to co= ply with MP-25.
11 79 XII 3
MI-25 Welding Instruction P-5-5-BA Revised to comply with MP-25.
11-29-79 XII 2
MI-25 Welding Instruction P-1-1-BA Revised to comply with MP-25.
11-29-79 VIII 0
RC&T-0130 - Airborne Radioactivity Analysis of Service Air for Breathing Purposes - Original issuc 11-29-79 VIII O
RC&T-0250 - Posting of Area Materials - Original issue of this procedure.
11-29-79 VIII O
RC&T-0260 - Inicial Entry into Areas Where Radio-logical Hazards are Unknown - Original issue.
11-29-79 VIII 0
RC&T-0030 - General Ins tru entation Checkout -
Original issue of this procedure.
11-29-79 VIII 0
RC&T-0501 - Operating Procedure for Ustag 200 Ci "Cs-137 Source and Manipulator - Original issue.
11-29-79 VIII 0
RC&T-3250 - Groundwater Monitoring Program -
Original issue of this procedure.
11-29-79 VIII O
RC&T-1140 - Kine =atic Viscosity of Transparent Opaque Liquids - Original issue of procedure.
11-29-79 VIII O
RC&T-0200 - Personal Exposure Control to Ionizing Radiation - Original issue of this procedure.
11-29-79 VIII O
RC&T-0240 - In-Vessel Work Procedure - Original issue of this procedure.
11-29-79 VIII O
RC&T-0241 - Drywell Work During Spent Fuel Movements - Original issue of this procedure.
11-29-79 VIII O
RC&T-1220 - Datermination of 200/5 uCi/ gram
- Original issue of this procedure.
11-29-79 VIII 0
RC&T-1260 - Determination of Decay Correction for Radioisotopes - Original issue of this procedure.
11-29-79 VIII O
RCST-1230 - Tritium Analysis of Liquid Effluents
- Original issue of this. procedure.
11-29-J9 VIII O
RC&T-0009 - Radiation Control and Protection -
Original issue of this procedure.
11-29-79 VIII O
RC&T-2010 - Radioactive Liquid Effluent Releases and Reports - Original issue of this procedure.
Deleted procedure 0008.
Ol'M:AT!!!C !!A:;t!A1. IT.0CI;!)tg:_Cl!A::GES REV.
DATC V%.
- 0.
NCDCR & TITLE /CIIA :"I 11-29-75 VIII O
RC&T-2020 - Stack and Building Vent Radioactive Gaseous Release Setpoints - Original issue of this procedure. Deleted procedure 0007.
11-29-79 VIII O
RC&T-3100 - Radiological Environ = ental Monitoring Program - Original issue.
Deleted procedure 0005.
11 79 VIII O
RCST-0300 - Instrument Calibration Control -
Ori'ginal issue. Deleted procedure 0004 11 75 VIII 0
RC&T-1000 - Sampling and Analysis Schedule for Radioactive and Nonradioactive Che=is try -
Original issue. Deleted procedure 0002.
11 75 VIII O
RC&T-2202 - Opsration and Calibration on Packard Liquid Scintillation Counter - Original issue.
11 75 VIII O
RC&T-2203 - Calibration and Operation of Particu-late Counters - Original issue of this procedure.
1 1 79 VIII O
RC&T-3110 - Emergency Environmental Monitoring
.- Original issue of this procedure.
11-30-79 XII 1
MI-ll GE Power Relay Checkout for Model 12IC'451A - Revised to co= ply with NRC and CQA requirecents.
11-30-79 I
6 AI PNSC Administration - Updated and added Ek. 1 for=s, one of which ensures that Tech. Spec.
violations are reviewed for being unreviewed safety questions.
11 79 VIII O
RC&T Procedure 0610 - Emergency Medical Treatment of Contaminated Patients - Updated and revised for RCST Instruction 7025 to RC&T procedure.
11-30-79 VIII 0
RC&T Procedure 0510 - Shipment of Radioactive Material - Original issue of this procedure.
12-6-79 XII O
MI-3-4D3 - VA-FR-3356 Bailey Recorder Model SR1310
- To meet CQA and NRC consit=ents.
12-6-79 XII O
MI-3-3A35 - S'J-PS-1995,1996,1998 and 1999 Service
'Jater to D/G - To meet CQA and NRC co=mitments.
12-6-79 I
1 AI-10.1 - Receiving the Spent Fuel Shipping Cask -
3k.2 Revised title and added note to allow use of Sunny Point or Pfizer train engine.
12-6-79 XIX 1
FP Control of Combustible Materials and Ignition Sources - Comprehensive revision to meet numerous NRC consitments and to reflect current organization.
OPERATIMC f tANtfAL P!tOCEDl!!E CllANCES REV.
DATE VOL.
MO.
NUlmER 6 TITLE /CilANCE 12 79 X
2 PT-46-3PC - Control Building Chlorine Detection
~
System Calibration - To return PT to original (revision 0) condition in accordance with vendor recocmendation.
12-7-79 X
13 PT-8.2.4 - RHR Service Water System Component Test
- Add flush procedure reference to PT and add new data to PT.
12 79 XII 0
MI-16-576 - Repair of Cll-LIS-N013E and F
- Original issue of this procedure.
12-12-79 VIII O
RC&T-0212 - Decontamination for Areas, Materials, Tools and Shipping Casks. Original issue.
12 79 VI 10 EI-27.3 - Abnormal Release of Rad.ioactivity-Airborne - Provided exa=ples of isopleths.
12 79 XVI 2
Annunciator Procedure A-5, _ Window 3 Reactor Vessel Hi Pressure Trip - Corrected setpoint for Unit No. 1.
12-18-79 X
8 PT-24.2 - Containment Atmosphere Monitoring System Component Test - Corrected stem column and listed penetration locations.
L2-I S-79 X71 1
Annunciator Procedure A-5, Window 3 Reactor Vessel Hi Pressure Trip - Corrected stepoint on Unic No. 2.
L2 79 X
12 PT-13.1 - Reactor Recire. Loops / Jet Pump Oper-ability - C1.*rified the procedure.
L 2-18-79 III 22 OP Residual Heat Removal System (RHR) - Added a step to reset LPCI initiation logic.
L 2-18-79 III 24 OP Containment Atmosphere Control System -
Added a precaution on running SBGT fans.
L 2-lS-79 VI 3
EI Reactor Building Closed Cooling Water System Failure - Added the closing of containment isolation valves.
.2-18-79 X
2 PT-25.1 - Nuclear Steam Supply - Added fuse numbers and a precaution when testing MSIVs on loss of power.
2 79 III 15 OP Control Rod Drive System - Added a procedure for verifying a stuck collet.
12-18-79 N/A 0
SP-79 Safety-Relief Valve Discharge Line Load Test - Original issue of this procedure.
OPEltATf!!C !! ant!AI. P!tCCI:nt!!m CllA!!CES REV.
DATC VnL.
- 0.
NU!T.ER L TITLE /C11A!!CE 12 7J XIII 12 E=ergency Plan - Added the technical support center and revised the organi:ational titles and responsibilities.
12-19-79 I
32 Administrative Procedures - Revised to update per the new organization and to meet Three Mile Island reco=mendations.
12 79 I
O AI Protective Coatings - Original issue.
12 75 XII 1
MI-1 ID-100 Ti=e Respense Test Set -
Revised to comply with MP-1.
e 12 79 XII 2
MI-3-1P3 - 321-LIS -NO31A-D Yarway Level Switch -
Added new setpoints per Plant Mod 79-216.
12 79 XII 2
MI-1 Fisher Controls TS112 ac' Field Tes t Unit - Revised to comply with MP-1 and updated.
12-19-79 XII 1
MI-10-lE - Bailey Go/Line and SR Strip Chart Recorders - Revised to comply with format of MP-10.
12 79 XII 2
MI-10-lD - Bailey Type 731 and 732, GE Type 520, 521, 530, 531 Strip Chart Recorders - Revised to comply with the for=at of MP-10.
12 79 XII 2
MI-10-lC - GE Strip Chart Recorders, HG Revised to comply with the format of MP-10.
12 79 XII 1
MI-26-lH - Remote Shutdown Reactor Water Level High Loop Calibration - Revised to satisfy CQA and NRC requirements.
12-19-79 XII 2
MI-ll GE Overcurrent Relay Checkout for Type IAC66K - Revised to ec= ply with format of MP-10.
12-19-79 XII 6
MI-10-1B - 3ristol Series 550 Dynamaster Recorders
- Revised to compl" with the for=at of MP-10.
12-19-79 XII O
MI-3-33A - C32-K615 Proportional A=plifier Type 563 original issue..
12 79 XII 0
MI-3-3A36 - MS-PSL-890 Barksdale Pressure Switch D2T-M150SS - Original issue.
12-19-79 XII O
MI-3-7F1 - VA-FY-3356-3, 335 7-3, 335 8-3 Moore I.IT Module - Original issue.
12 79 XII O
MI-3-4P1 - GEN-WMR-760 Watt =eter Recorder -
Original issue.
12 79 XII 0
MI-3-4C5 - CDD-CJRS-1 Condensate Deep Bed Demin-erali:er L&N Speedomax Recorder - Type 'H' Orief a31 4asue-
OPERATf!!C !!A;;tfAL PitOCI: Dill:1: Cll A:"GES W
REV.
DATL
'!9 L.
- 0.
NU:3ER 6 T1TLE/CHA::CE 12 79 XII 0
MI-3-5 AD1 - VA-PDC-3309, 3010, 3011, 3012 Control-ling Receivers Model T90ll - Original issue.
12 79 XII 0
MI-3-231 B21-F1-R609A-D, GE Type ISO Meter
- Original issue.
12 79 XII 0
MI-3-1BP1 - Moore Square Root Module - Original issue.
12 79 XII 0
MI-3-455 - CAC-AR-L264 LSN Recorder - Original issue.
I
~
12 l9-79 XII 0
MI-3-1J1 - VA-FT-3150 Bailey Transmitter -
Original issue.
12-19-79 XII O
MI-3-1J2
.VA-FT-3151 Bailey Transmitter -
Original' issue.
12 79 XII O
MI-3-2A1 - IA-PI-3785 U.S. Gauge-1900 Series -
Original issue.
12 79 XII O
MI-3-3A37 - Barksdale Pressure Switch Model
'D2T-M150-SS-L6 - Original issue.
12-19-79 XII 0
MI-3-2Q1 - Sigma Level Indicating Gauge -
Original issue.
12 79 XII 0
MI-3-3F1 - SW-FS-89 7 - Service Water-Flow Switch
- Original issue.
12 79 XII 0
MI-1 Battery Ther=oceter - Original issue.
12-19-79 XII O
MI-3-4C2 - L&N Speedo=ax Multipoint Conductivity Recorder Type 'H'
- Original issue.
12 79 XII O
MI-3-4D9 - CAC-LR-2602 Suppression Cha=ber Level Recorder - Original issue.
12 79 XII 0
MI-3-3A34 - SW-PS 1175 and 1176 Service Water Pressure Switch - Original issue.
12 79 XII O
MI-3-4F1 - G16-FR-115-660 Taylor Flow Recorder
- Original issue.
12-19-79 XII O
MI-3-4L1 - VA-AR-3215, 3216, L&N Recorder, Model M
- Original issue.
12 79 XII 0
MI-3-1B01 - VA-TT-3447, 3360, 3361 Moore RST Module
- Original issue.
12 79 XII 0
MI-3-3Q 1 - VA-KS-1026-102 7 - Johnson Time r:opor-tioning Switch - Original issue.
12 79 XII 0
MI-3-3A38 - 3arksdale Pressure Switch Model D2T-M150-SS - Oricinal 4.m m
OPEltATl!!C ?!A::tIA1. I't:0CI:!)t!!:E CllA::CES REV.
DATE VOL., i:0.
NLS EP. 6 TITLE /Ci!.UfT 12 79 XII 0
MI-3-4D7 - CAC-FR-26 87, N, Flow Recorder
~
- Original issue.
12 79 XII O
MI-1 Battery Hydro =eter Type EBS 13090 -
- Original issue.
12 75 XII 1
MI-16-532 - Reactor Recirculation Pucp3 - Added the tack welding of lock pins and QA hold points.
12 75 XII 1
MI-16-501 - Instructions for Re= oval and Cleaning CRD Drive Water Filter - Added torquing and cleanliness hold points.
12 75 XII 1
MI-16-532A - Reactor Recirculation Pump Mechanical Seals - Added cleanliness hold points, referenced MP-12, anc. deleted. references to MMI-32.
12 79 XII 4. MP Qualification of Weld Procedure Specifi-cations and Welders - Added QA review, restated welder's requirements, included welder's requalifi-cation records and forms.
12 79 N/A 0
.SP-79 RPV Bottom Drain Flush - Original issue.
12-20-79 XII 4
MP Writing Corrective Maintenance Instructions
- Revised to co= ply with ANSI and CQA requirements.
12-20-79 XII 11 MP Preventive Maintenance Program - Revised to comply with ANSI and CQA require =ents.
12 79 XII 1
MI-16-535 - Standby Gas Treat =ent System
- Added QA hold points.
12 79 XII 1
MI-16-564 - Nuclear and Conventional Service Water Lube Water Pumps - Revised to comply with MP-16.
12 79 XII O
MI-10-515B - Pu=p Vibration Readings Service Water
/Cire. Water - Original issue.
12-2 1-79 IV 53 GP General Plant Operating Procedure - Revised to provide protection during a loss of feedwater during a reactor startup, to ensure the LPCI mode of RER is available after changing from shutdown-cooling, to put the RFP Into service and updated.
12 79 VII 0
OI Annunciator Status - Original issue.
12-2 7-79 VII O
OI Diesel Generator Operability - Original issue.
12-2 7 -79 VII 0
OI Meteorological Data Collection - Original issue.
12-2 7-79 VII O
OI Drywell Closecut and Inspection - Original issue.
12 79 III 10 OP Nuclear Boiler System - Revised to incorpor-ate Plant Modification 79-258.
4 Ol'ERATT:!C ttA;;tfAI.11ROCI:!{lli:1: Cll A:'CES REV.
DATE VOL.
50.
NU:?CR 6 TITLE /CIIA:'CE 12-27-79 VII O
OI Control of High Radiation Areas Where Level:
~
Exceed 1000 MR/ER - Original issue.
12-27-79 IV 7
EI Plant Shutdown from Outside Control Room -
Revised to incorporate Plant Mods79-215 & 79-216.
12-27-75 III 23 OP RER System - Revised to incorporate Plant Modif cations79-215 and 79-216.
li
-75 VIII 0
RCST-2150 - Calibration of Plant In-Line Conducci-vity Cells - Original issue.
12-2 7-79 VIII 0
RC&T-0301 - Calibration of Hand and Foot Monitors
- Original issue.
12 79 VIII O
RC&T-0310 - Calibration of NMC Co.ntinuous Air Monitors (CAMS) - Original issue.
12-2 7-79 VIII O
RC&T-0313 - Staplex High Volume Air Sampler Type TFIA - Original issue.
12 79 VIII O
RC&T-0350 - Leak Testing and Calibration for Self-
' Reading Pocket Dosi=eters - Original issue.
12-27-79 VIII 0
RC&T-0331 - Calibration for the Eber11ne Portable Neutron REM Counter Model PNR Original issue.
12-27-79 VIII O
RC&T-0321 - Calibration of the RM-16 Radiation Monitor - Original issue.
12 79 VIII O
RC&T-0322 - Calibration of the Teletector, Model 6112 and Model 61123 - Original issue.
12-2 7-79 VIII 0
RC&T-0302 - Calibration of Portal Monitors -
i Original issue.
12 79 VIII O
RC&T-0340 - Calibration of Eberline Portable Scin-tillation Alpha Counter Model PAC-4S - Original issue.
12-27-79 VIII 0
RC&T-0326 - Calibration of the PRM-7 Micro R/RR Meter - Original issue.
12-2 7-79 VIII O
RC&T-0324 - Calibration of Eberline E-520
- Original issue.
12-27-79 VIII O
RC&T-0325 - Eberline Portable Ion Chanber Model PIC-6A - Original issue.
12-27-J9 VIII 0
RC&T-0323 - Eberline Portable Geiger Counter Model E-400 - Original issue.
12-27-79 VIII O
RC&T-0330 - Calibration of Eberline Portable Fast-Slow Neutron Counter Model PNC-4.- Original issue.
OJI:HATf MC !!AtiUAI. I'! 0CI:DUi:!: Cil A:!C"S REV.
Df.TC VOL.
':0.
NLDEM t. TITLE /Cl!M:f:C 12 79 VIII 0
RC&T-0320 - Calibration of Eberline RM-14 Radiatior Monitor & Ludlum 177 Alarm Rate Meter with the HP-210 Probe - Original issue.
12-27-79 VIII O
RC&T-0312 - Hurricane High-Volume Air Sampler Model 16003 - Original issue.
12-27-79 X
3 PT-50.0 - Post Refueling Outage'Startup Testing
- Revised to add a reactivity anomaly check.
12 79 X
2 PT-50.3 - TIP Reproducibility - Revised to annotatc the computer program printout.
12 79 X
1 PT-50.3.1 - Total TIP Uncertainty - Revised to annotate the computer program printout.
12 79 VIII 0
RC&T-0511 - Collection and Prepar'ation of Resin Batch and Liner Samples for Analysis - Original issue.
~
12-27-79 VIII O
RC&T-0600 - RC&T Emergency Actions for Site Evacuation - Original issue.
12-27-79 VIII 0
'RC&I-0261 - Drywell Entry - Original issue.
12-27-79 VIII 0
EC&T-1210 - Determination of Radiciodine - Origina:
Issue.
12-27-79 X
0 PT Process Radiation Monitors-SW Ef fluent -
Original issue.
12-27-79 X
0 PT Process Radiation Monitors - RBCCW
- Original issue.
12-27-79 X
0 PT-77.1 - Chloride Intrusion Monitor Calibration (Hotwell Legs) - Original issue.
12-27-79 X
0 PT-77.2 - Chloride Intrusion Monitor Calibration
- Original issue.
12-27-79 X
0 PT Drywell Radiation Monitors - Channel Calibration - Driginal issue.
12-27-79 X
0 PT Reactor and Turbine Building Roof Vent Radiation Monitors Channel Calibration - Original issue 12 79 XII 4
MP Corrective Maintenance - Revised to conforr to MMS (Maintenance Management System) and add approval by each Maintenance Supervisor.
12-31,79 XII 1
MI-16-558 - Nuclear and Conventional SW Pumps
- Revised to comply with MP-16.
12-31-79 XII 0
MI-16-503B - 3" and 8",150# Anchor Globe and Angle Valves - Original issue.
k
OPEl:ATl!!C !W;tfA!, l'!!OCI:1)(!! !; _Cl!AMCES REV.
DATE VOL.
?:0.
NimCR S TITLE /Cl!A::GC 12 79 XII 1
MI-16-545 - Main Steam Safety Relief Valves -
Revised to comply with MP Added hold points and added a step for resetting pilot valve.
12 75 XII 2
MI-16-524 - Nordberg Diesel Generators - Revised to comply with MP-16.
12 75 XII 1
MI-10-509 3 - Irradiated Fuel Shipping Cask Redun-dan: Lif ting Yoke - Revised to comply with MP-10.
12 79 XII 1
MI-10-505A - PM for Goulds Su=p Pump Model 3137-5
- Revised to co= ply with MP-10 and to incorporate technical manual changes.
12 79 X
2 PT-60.1 - Six-Inch Fuel Pool Cooling Check Valves
- Revised to add review for cleanliness and to clarify the use of alignment dowel pins.
12-31-79 XII 1
MI-10-503A - E=ergency Diesel Generators Annual Inspection - Revised to comply with MP-10.
12 79 XII 1
MI-10-509A - Sterns-Rogers Refueling Platform
.- Revised to comply with MP-10.
12-31-79 XII 14 MP Calibration of Process Instruments - Revised to meet CQA and NRC requirements.
12-31-79 XII 0
MI-3-521 - G41-FRCS-85 Foxboro Controller Recorder Model 58P4F - Revised to meet CQA and NRC requirements.
12 79 XII 0
MI-3-3A39 - Barksdale Pressure Switch Model DZT-Ml50 SS - Revised to comply with CQA and NRC requirements.
12 79 N/A 0
SP-79 Safety-Related Drywell Equipment Electrical Termination Solution and Inspection -
Original issue for Unit No. 1.
12 79 XII 5
MI-10-1A - L&N Speedomax M, Multipoint Recorder, Mark II and Ma'rk.III - Revised to conform to CQA and ANSI requirements.
12-31-79 1
33 Administrative Procedures - Revised to update the Equipment Clearance Form, to add a " housekeeping" procedure, and to add QA to.ae review of OERs to ensure 10CFR21 requiremente are met.
12-31-79 VII 0
OI LCO Evaluation and Followup - Original issue 12-31-79 VII 0
0I Operating' Principles and Philosophy -
Original issue.
12 79 XII 1
MI-10-2AA - Refuel' Platform.- Revised to comply with MP-10 and updated.
OPFitATII:C MA:;tfAI. P!:CCr.Dt!I:M CllA!!CES REV.
DATE VOL.
- 0.
NIRGER 6 TITLE /CIIA!!GE 12-31-79 XII 0
MI-3-8C1 - A0G-0 A-108 Delphi Oxygen Analy:er 3
- Original issue!
12-31-79 XII O
MI-3-4D5 - SCW-LR-285 Bailey Type SR-1110 Level Recorder - Revised to comply with CQA and NRC requirements.
12-31-79 XII O
MI-3-4C6 - TS-AR-868 L&N Speedomax Recorder Type H
- Original issue.
12-31-79 XII 1
MI-10-lG - Taylor 1300 Series Strip-Chart Records
- Revised to comply with MP-10.
12-31-79 X
0 PT Process Radiation Monitors - Original issue 12-31-79 X
0 PT Of f-Gas Radiation Monitor Channel Calibration - Original issue.
12-31-79 X
0 PT Main Steam Line Monitor Channel Calibration - Original issne.
12-31-79 VIII O
RC&T-1215 - Analysis for Strontium-Yttrium -
Original issue.
12-31-79 VIII O
RCST-1100 - Chemical Release - Original issue.
12-31-79 VIII 1
RC&T-2010 - Radioactive Liquid Effluent Releases and Reports - Revised tabulation form to update.
12-31-79 VIII 0
RC&T-0050 - Response Testing of RC&T Portable Survey Instrumentation - Original issue.
12 79 VIII O
RC&T-0311 - Bell and Gossett Low-Volume Air Sampler - Original issue.
12-31-79 VIII O
RC&T-1500 - Collection and Preparation Procedure -
for Reactor Water Af ter a Fuel Element Accident -
Original issue.
12 79 VIII 1
RC&T-1211 - Analysis for Radiciodine in Iodine Collection Car'tridges and Filters - Revised to provide a means to remove excessive Xe-133 gas from iodine collection chrtridges.
12-31-79 XIV 4
Special Nuclear Material Accountability Plan -
Revised to update and incorporate recent NRC requirements.
12 79 XI-0 QAP Receiving Inspection of Q-List Material and Components
,0riginal issue.
12 79 I
O AI BSEP Program for Compliance to 10CFR21 -
Bk.2 Original issue.
OPERAT!!;C !!Aut AL PROCEntH:P. C!lA::CES W
REV.
D,"*.T E VOL.
50.
NU!C\\CP 6 TITLE /CIIA!'CE 12-3 1-7 VII O
OI Operations Work Procedures (0WP) Prepara-tion and Execution - Original issue.
12 79 IV 7
OG Operations Work Procedure - Deleted OG-7.
Replaced by OI-10.
12-31-79 VII O
01 Shif t Turnover Checklist - Original issue.
12 79 VII 0
01 Periodic Testing and Daily Surveillance Report - Original issue.
12-31-79 VII 0
OWP-1/6 - Repairing Frayed or Da= aged Wiring to Safety / Relief Valve Pilot Assemblies F013E and F013H - Original issue.
12 79 VII 0
OWP-1/4 - Replacement of Motor fo.r B21-F019
- Original issue.
12 79 VII 0
OWP-1/2 - Feedwater Sparger Replacement - Original issue.
12 79.VII 0
ORP-1/1 - Removal of Safety / Relief Valve Pilot Assemblies for Inspection and Repair - Original issue.
12-31-79 VII 0
OWP-2/1 - Repair Tes t Connection on Reactor Recirculation System Piping not Within Isolation Valves - Original issue.
12-31-79 VII 0
CWP-5/2 - Remove SLC Pump A from Service to Change 011 - Original issue.
12 79 VII 0
ok?-5/3 - SLC Relief Valve F029A(B) Repair -
Original issue.
12-31-79 VII O
OWP-2/2 - Reactor Recirculation Pump Seal Replace-cent - Original issue.
12 79 VII O
OWP-1/5 - Replace Level Instrument Manifold on B21-LIS -NO31B with the Manifold from B21 -LT-N0263
- Original issue.
12 79 VII O
OWP-5/1 - SLC Pumps - Original issue.
12 79 VII 0
GWP-1/3 - Reactor Vessel Water Level Control While Installing CRD Thermal Barrier and Cutting and Capping of both C.S. Lines Outside the Manual C.S. Isolation Valve - Original issue.
12-31-79 VI 3
EI Condensate & Feedwater Failure - Revised to incorporate Three Mile Island (TMI) review.
12 79 VI O
EI-l.3 - Small Break Outside Drywell - Original issue.
12-31-79 VI 12 EI-1.1 - Primary System Rupture Inside Drywell (Leaks) - Revised to incorporate IMI review.
s
- OPERATING MANUAL PROCEDURE CHANCES DATE VOLUME NUMBER & TITLE / CHANGE 12-31-79 VI 10 EI-1.2 - Rupture Inside Drjwell - Revised to incorporate TMI review.
12-31-79 VI 5
EI Abnormal Reactor Water Levels - Revised to incorpora;e TMI review.
12-31-79 VI 10 EI Safety / Relief Valve Fails Open - Revised to incorporate TMI review.
s e
.n