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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] Category:TEST REPORT
MONTHYEARML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20096B4311995-12-31031 December 1995 Cycle 11 Startup Rept ML20078S9501994-12-16016 December 1994 PBAPS Cycle 11 Startup Rept for Unit 2 ML20063J9191994-02-10010 February 1994 Cycle 10 Startup Rept ML20101S9401991-12-31031 December 1991 PBAPS Unit 2 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20090L8131991-12-24024 December 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML20082B9391991-07-17017 July 1991 Rept of Plant Start-Up Following Eighth Refueling Outage on 910112-0412.W/undated Ltr ML20079C9511991-03-29029 March 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML19332C8201989-11-17017 November 1989 Rept of Plant Startup Following Seventh Refueling Outage, 870315-891010. W/891117 Ltr ML20244C2571989-01-31031 January 1989 Reactor Containment Bldg Integrated Leak Rate Test ML20155G1931988-10-31031 October 1988 Rept on Restart Review Panel Assessment of Readiness for Restart ML20155J8451988-05-27027 May 1988 App R Multiple High Impedance Cable Fault Flame Test Rept ML20154C7101988-05-0606 May 1988 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20138Q9771985-10-28028 October 1985 Rept of Plant Startup Following Sixth Refueling Outage, 840428-850713 ML20135D5431985-06-11011 June 1985 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20126J8401985-05-30030 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 51,Unit 2,3,Turbine Bldg El 135 Ft Corridor to Switchgear Rooms,Fire Area 78A ML20126J9901985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 97,Unit 2,3,Turbine Bldg El 116 Ft Janitor Room,Fire Area 116 ML20126J9761985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 96,Unit 2,3,Turbine Bldg El 116 Ft Toilet Area,Fire Area 115 ML20126J9521985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 95,Unit 2,3,Turbine Bldg El 116 Ft Clean Clothes Room,Fire Area 114 ML20126J9261985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 94,Unit 2,3,Turbine Bldg El 116 Ft Counting Room,Fire Area 78E ML20126J9091985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 93,Unit 2,3,Turbine Bldg El 116 Ft Health Physics Util Room,Fire Area 82 ML20126J8861985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 92,Unit 2,3,Turbine Bldg El 116 Ft Conventional Chemistry Lab,Fire Area 78D ML20126J8581985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 91,Unit 2,3,Turbine Bldg El 118 Ft Radiation Chemistry Lab,Fire Area 78C ML20126J8251985-05-20020 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 24,Unit 2,3,Turbine Bldg El 116 Ft Common Equipment Area (Beneath Switchgear Rooms),Fire Area 78B ML20238D8651985-02-28028 February 1985 Hydrogen Water Chemistry Mini Test Final Rept. W/Two Oversize Drawings.Related Info Encl ML20092D7071984-06-20020 June 1984 Ultrasonic Indications in Jet Pump Instrumentation Penetrations of Peach Bottom Atomic Power Station,Unit 3 ML20084R3001984-03-14014 March 1984 Fire Endurance & Hose Stream Tests on Floor Penetration Fire Stops Design Fc 350 ML20084R2921984-02-16016 February 1984 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design Wp 713 ML20082N3381983-12-31031 December 1983 HVAC Damper Program Penetration Seal Test Results & Exemption Requests ML20084R2881983-11-0404 November 1983 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design WP694 ML20082G1231983-08-23023 August 1983 Reactor Containment Bldg Integrated Leakage Rate Test Rept, Conducted During Aug 1983 ML20080F9801983-02-14014 February 1983 Rept of Plant Startup Following Fifth Refueling Outage, Feb 1983 ML20027C3241982-02-28028 February 1982 Rept of Plant Startup Following Fifth Refueling Outage, 820219 ML20039B6801981-09-0606 September 1981 Primary Reactor Containment Integrated Leakage Rate Test Rept. ML20041C8071981-03-0707 March 1981 Rept of Plant Startup Following Fourth Refueling Outage, 810307. ML20062K2481980-07-28028 July 1980 Primary Reactor Containment Integrated Leak Rate Test ML19345A8241980-03-31031 March 1980 Rept of Plant Startup Following Fourth Refueling Outage, Mar 1980. ML19344D2631980-03-0505 March 1980 Rept of Startup Following Third Refueling Outage,Sept 1979. ML19274D3301978-10-31031 October 1978 Rept of Plant Start-up Following Third Refueling Outage Sept-Oct 1978. Assures That Unit 2 Refueling Outage Caused No Conditions or Sys Characteristics to Diminish Safe Operation ML20081B9871977-04-0404 April 1977 Reactor Containment Bldg:Integrated Leakage Rate Test Rept ML20072N7491975-07-22022 July 1975 Noise Level Measurements Surveillance Test Results ML20072N7551975-04-30030 April 1975 Noise Level Measurements Surveillance Test Results ML20072N7781974-10-29029 October 1974 Noise Level Measurements Surveillance Test Results ML20072N7611974-07-25025 July 1974 Noise Level Instruments Surveillance Test Results ML20072N7701974-02-24024 February 1974 Noise Level Measurements Surveillance Test Results 1998-12-31
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l PHILADELPHIA ELECTRIC COMPANY PHILADELPHIA I
PEACH BOTI'OM ATOMIC POWER STATION UNIT NO. 2 DOCKET NUMBER 50-277 I '
I REPORT OF PLANT START-UP FOLLOWING FIPI'H REFUELING OUTAGE FEBRUARY 1982 I
I s-THE UNITED STATES NUCLEAR REGULATORY C0 EMISSION PURSUANT TO FACILITY OPERATING LICENSE NO. DPR-1144 I
I P 38vagn, -
PDR
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PHILADELPHIA ELECTRIC COMPANY I
,3 Peach Bottom Atomic Power Station E Unit No. 2 Docket Number 50-277 REPORT OF PLANT START-UP FOLLOWING FIFTH REFUELING OUTAGE FEBRUARY 19, 1982 SUBMITTED TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSEE DPR-44 Preparation Directed By:
I W. T. Ullrich, Superintendent Peach Bottom Atomic Power Station RD #1 Delta, PA 17314
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Page 2 TABLE OF CONTENTS INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . .3 I
SUMMARY
OF TESTS
- 1. Verification of Shutdown Margin . . . . . . . . . . . . . . . . .4
- 2. Control Rod Operability and Subcriticality Check. . . . . . . . .4
- 3. LPRM Calibration. . . . . . . . . . . . . . . . . . . . . . . . .4
- 4. Reactivity Anomalies. . . . . . . . . . . . . . . . . . . . . . .4
- 5. Core Verification . . . . . . . . . . . . . . . . . . . . . . .4,5
- 6. Cold Critical Rod Pattern Prediction. . . . . . . . . . . . . . .5
- 7. Core Power Symmetry and TIP Reproducibility Test. . . . . . . . .5
- 8. Control Rod Drive Scram Timing. . . . . . . . . . . . . . . . . .5
- 9. CRD Scram Discharge Volume Modifications (Mod 655) . . . . . . .5,6
- 10. Reactor Water Level Full Range Recorders (Mod 576A) . . . . . . .6
- 11. Auto Swap Over of RCIC Suction (Mod 635) . . . . . . . . . . . . .6
- 12. Post Accident Monitoring of Torus Level (Mod 584B) . . . . . . . .6
- 13. High Range Containment Rad Monitors (Mod 587) . . . . . . . . .6,7
- 14. MSRV/ Safety Valve Acoustic Monitoring (Mod 575) . . . . . . . . .7
- 15. Removal of Mod 641 and 680 (Mod 964) . . . . . . . . . . . . . . .7
- 16. Drywell Pressure Instruments (Mod 584A) . . . . . . . . . . . . .7
- 17. ADS N2 Supply Headers (Mod 625E) . . . . . . . . . . . . . . . . .7
Page 3 INTRODUCTION 1
i The Peach Bottom Technical Specification 6.9.1 Routine Reports requires submittal of a startup report following any outage in which certain safety related events may occur.
Installation of fuel of a different design is one of these events. This report, prepared to meet the Technical Specification requirement, describes the startup program )
implemented to provide assurance that the safe operation of the plant was not diminished by the activities of the fifth refueling ,
outage. j The Peach Bottom Unit 2 was out of service from February 19, 1982, to June 25, 1982, to accommodate a maintenance and refueling outage. During this 116 day outage, 224 bundles of the (8x8) design, 49 (8x8R), 2 (LTA), and 1 (P 8x8 R) were replaced with 276 bundles of the (P 8x8 R) fuel design. The reactor was returned to service on June 25, 1982, and reached full power on July 12, 1982. Start-up tests were performed before and during the return to power.
I The startup tests identified in the F.S.A.R. were addressed and those which involve areas which were affected by outage activities were included and are summarized herein. Additional special tests connected with specific outage activities were also included in the program and are discussed in this report. The successful implementation of this startup program insures that the Unit 2 refueling outage has resulted in no conditions or system characteristics that in any way diminish the safe operation of Unit 2.
The tests and data referenced in this report are on file at the Peach Bottom Atomic Power Station.
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STARTUP REPORT Peach Bottom Atomic Power Station UNIT NO. 2
- 1. VERIFICATION OF SHUTDOWN MARGIN An 'in-sequence' SDM determination was performed during the initial reactor startup in the A sequence. The actual shutdoun margin was 2.09% delta K/K, as compared with a Technical Specification minimum value of 0.38% delta K/K + R, where R = .29% delta K/K. This test was performed on June 25, 1982.
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- 2. CONTROL ROD OPERABILITY AND SUBCRITICALITY CHECK I Each control rod was withdrawn and inserted. Suberiticality was verified per surveillance test ST 10.8. The test was completed on June 24, 1982, prior to start-up.
LPRM CALIBRATION 3.
LPRM calibrations were successfully performed at approximately 34% Rated Thermal Power (RCTP), on July 3, 1982 and at 98% RCTP on July 14, 1982 per surveillance test ST 3.4.1.
- 4. REACTIVITY ANOMALIES I Surveillance test ST 3.7, " Reactivity Anomalies", was successfully performed on July 19, 1982. The predicted number of control rod notches inserted at rated conditions was 600 with a + 1% delta Keff range of 800 to 400 control rod notches inserted. The actual number of control rod notches inserted was 444, which satisfies the + 1% delta Keff -
criteria.
- 5. CORE VERIFICATION I Post alteration core verification began on May 20, 1982, in accordance with surveillance test ST 12.10, " Core Post-Alteration verification" with the exception of the bundles surrounding cell 26-23. Cell 26-23 could not be verified at i that time due to an assembly being dropped in that cell. The seating verification revealed several assemblies to be improperly seated at this time. On May 29, 1982, cell 26-23 and the surrounding bundles were verified and all previously identified improperly seated bundles in the core were
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I Page 5 reseated and reverified. All fuel bundles were verified to I be correctly located, seated, and oriented prior to Cycle 6 startup and operation.
- 6. COLD CRITICAL ROD PATTERN PREDICTION I The cold critical rod pattern prediction comparison surveillance test ST 3.9 was successfully performed for Unit
- 2. The predicted core keff was 1.002 and the actual core lI i
keff was 1.003 for a difference of .001. The difference is
-0.1% and satisfies the + 1% test acceptance criteria.
- 7. CORE POWER SYMMETRY AND TIP REPRODUCIBILITY TEST Two sets of core power symmetry and TIP reproducibility test data were analyzed for sequence 'A' conditions on July 22, 1982 and August 4, 1982 at rated power. The total TIP uncertainty was 4.99% and 4.77% for the two sets; therefore, the test criteria that the total TIP uncertainty not exceed
. 8.7% is satisfied. The maximum deviation between symmetrically located pairs was 12.3% and 12.6% for the two data sets respectively, which satisfies the 25% acceptance criteria.
- 8. CONTROL ROD DRIVE SCRAM TIMING
.I All 185 control rods were scram timed satisfactorily following all core alterations at nominal reactor pressure of 1000 psig, in accordance with surveillance test ST 10.7. The
'I test was begun on June 11, 1982 and all rods were scram timed with the exception of control rods 06-39 and 46-19. These two control rods could not be tested ut that time due to position indicating probe (PIP) problems. Following repairs, these two control rods were scram timed on July 2, 1982, completing the test and satisfying all Technical Specification requirements.
- 9. CRD SCRAM DISCHARGE VOLUME MODIFICATIONS (MOD 655)
The two inch piping between the scram discharge volumes and the instrument volume was replaced with piping equal in crtss sectional area to that used for the discharge volume. This II was done so that no restrictions will exist between the two discharge volumes and the instrument volume and there will be no dependence on the vent and drain system for the proper detection of water.
The piping for the level detection instrumentation was re-I routed such that it connects directly with the instrument volume to minimize the effects of transient loading on the level instrumentation resulting from vent and drain valve operation.
Page 6 Relief valve RV-34 was removed from the instrument volume drain line to eliminate the potential for release of reactor coolant following failure of this valve.
Redundant isolation valves on the discharge volume vent and drain line were installed in series with the existing valves.
Each valve is provided with its own pilot solenoid valve, which are actuated by the RPS system. Following a scram reset, the valves remain closed until opened from the Control Room.
A pre-operational test of the system was completed May 25, 1982.
I This modification was required by I&E Bulletin 80-17 and is now completed for both Unit 2 and Unit 3.
- 10. REACTOR WATER LEVEL FULL RANGE RECORDERS (MOD 576A)
Mod 576A fulfills the NUREG 0737 requirements for reactor I water level monitoring over the range of normal water level to the bottom of the fuel. There are two recorders in the Control Room. Each recorder has two channels, one for wide-range reactor level (-16 5" to + 5 0") and one for fuel-zone I level (-325" to 0"). The recorder inputs are obtained from Mod 576A.
- 11. AUTO SWAP OVER OF RCIC SUCTION (MOD 635)
Mod 635 added controls to automatically transfer RCIC pump suction to the torus from the condensate storage tank I (C . S .T . ) on low C.S.T. level. Two level instrument loops in a one out of two logic are used. The modification satisfies NUREG 0737 requirements.
- 12. POST ACCIDENT MONITORING OF TORUS LEVEL (MOD 584B)
I Mod 584B replaces existing torus water level instruments 2914 with new instruments qualified for post accident monitoring.
This mod satisfies NUREG 0737 " Clarification of TMI Action Plan Requirements". It was installed during the spring / summer 1982 refuel outage on Unit #2 and by July 8, 1982 on Unit #3.
- 13. HIGH RANGE CONTAINMENT RAD MONITORS (MOD 587)
This modification involved the installatici of four containment radiation monitors with a range of lx10 0 R/hr.
I The detectors are located in the drywell at elevation 142' at the 352 degrees, 279 degrees, 122 degrees, and 350 degrees azimuths. Radiation levels in the drywell are recorded and alarmed in the Control Room and on the process computer printout.
I Page 7 The purpose of this modification is to provide post accident drywell radiation information for emergency plant implementation.
- 14. MSRV/ SAFETY VALVE ACOUSTIC MONITORING (MOD 575)
This modification involved the installation of a direct method of indicating the position of the safety / relief valves and an indication and alarm system based on acoustic monitoring techniques. Each valve has its own channel of instrumentation consisting of a sensor mounted on the valve inside primary containment, a pre-amp mounted in the Reactor Building, an electronics module mounted in the Cable Spread Room, as well as indicating lights in the control Room. Red and green indicating lights indicate actual valve position for each valve, and an alarm and amber light indicate each valve that has opened. The plant process computer also records valve opening and closing.
- 15. REMOVAL OF MOD 641 AND 680 (MOD 964)
Mod 964 removed all alarms, indication, and actuation devices installed by Mod 641 (Scram Discharge Volume Water Level Continuous Monitoring System) and Mod 680 (Auto-Scram on Low Air Header Pressure). Both of these mods were installed I during the 4th refueling of Unit #2 as a result of NRC Bulletin 80-17. Mod 655 corrected the S.D.V. system during this outage such that 641 and 680 are no longer needed. Mods 641 and 680 were removed and the revised back-up scram valve logic was successfully tested on June 23, 1982.
- 16. DRYWELL PRESSURE INSTRUMENTS (MOD 584A)
Mod 584A provides instrumentation capable of monitoring containment pressure conditions during the course of an I accident. Four, quality assured, environmentally and seismically qualified instrument channels were installed to monitor drywell pressure. The outputs of these pressure transmitters are recorded on two control room ~ recorders.
Each record has two ranges (5 to 25 psia) and (0 to 225 psig). This pre-op was successfully completed for Unit #2 on July 2, 1982.
- 17. ADS N2 SUPPLY HEADERS (MOD 625E)
Mod 625E installed two seismically qualified ring headers inside the drywell. The connecting piping and valves to the five ADS relief valves were installed to provide a 100 day back-up N2 supply to the ADS valves.