ML20076E523
| ML20076E523 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/09/1983 |
| From: | Alden W, Fleischmann R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-2.K.3.22, TASK-TM IEB-80-17, NUDOCS 8308240515 | |
| Download: ML20076E523 (23) | |
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PEACH BOTTOM ATOMIC POWER STATION UNIT NOS. 2 AND 3 ANNUAL PLANT MODIFICATION REPORT January 1, 1982 through December 31, 1982 Submitted to The United States Nuclear Regulatory Commission Pursuant to
! Facility Operating Licenses Nos. DPR-M & DPR-56 l
Preparation Directed By:
i R. S. Fleischmann, II, Superintendent-Peach Bottom Atomic Power Station i
4 O R 8308240515 830609 PDR ADOCK 05000277 PDR
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PEACH BOTTOM ATOMIC POWER STATION UNIT NOS. 2 AND 3 ANNUAL PLANT MODIFICATION REPORT January 1, 1982 through December 31, 1982 O -
Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses Nos. DPR-Id4 & DPR-56 0
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PEACH EOTTOM ATOMTC POWER STATION ANNUAL PLANT MODIFICATION REPORT This report for Peach Bottom Atomic Power Station Units No. 2 and 3, License Nos. DPR-44 and DPR-56, is issued in fulfillment of the renortina recuirements of 10 CFR 50.50 It describes changes made to the facility as the facility is described in the safety analysis report. The report covers modifications that were complete in 1492.
For each of the modifications, tests or experiments included in this report, the safety evaluation performed indicated that an unreviewed safety auestion as defined in 10 CFR 50.59(a)(2) was not created; in that (i) the orobability of occurrence or the consecuences of an accident or malfunction of ecuipment important to safety previously evaluated in the safety analysis report was not increased, or (ii) a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report was not created, or (iii) the margin of safety as defined in the basis for any technical soecification was not reduced.
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\- Changes to the Technical Specifications were required for some of the modificati ons, tests or exneriments included in this report.
Those requirina Technical Specification changes are noted in the descriptions of the applicable modifications, tests or experiments.
l UNIT 2 l
Direct Indication of Main Steam Melief Valve Position I
Instrumentation A modi fication to replace the sensor electrical connections and cabl e used inside the drywell for the safetv/ relief valve position indication system was completed. This modification involved changing the connection between the mineral insulated cable at the sensor and the coaxial cable f rom a splice to an amphenol connector. Also, the cable in the drywell was chanced from coaxial cable to twisted shielded pairs. The purpose of this modification was to provide environmentally nualified equipment in the drywell.
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O Page 2 Main Steam Line Radiation Detector Cables A modification to install new cables on the main steam line radiation monitors was completed. This modification involved replacing the old RG59 B/U coaxial cables with Brand Rex CS 75146 cable which has a flame-retardent cross-linked polyethylene dielectric instead of polyethylene and rating of 190 degrees F instead of 120 degrees F. The purpose of this modification was to eliminate the embrittlement problems which had been occurrino as a result of heat and radiation degradation.
Containment Atmosphere Dilution System Tsolation Valves A modification to install Containment Atmosphere Dilution (CAD) system manual isolation valves (2"-130) in the exhaust lines to the standby gas treatment system was comnieted. This modification involved the installation of block valves in the O-listed 52MB-2" CAD exhaust line to standby gas treatment system
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% downstream of the flow elements in these two lines. The purpose of this me.dification is to pressure test (100 psio) the CAD exhaust panel tie-ins. ,
Reroute HPCI/RCTC Steam Leak Detection System Cable
- A modification to reroute HPCT and RCIC steam leak detection and l isolation instrument cables was completed. This modification l involved rerouting HPCI and RCIC steam leak detection cables in l their own conduits. The purpose of this modification is to meet segregation criteria and prevent loss of HPCI, RCIC or ADS upon l
failure of a specific tray.
Installation of Feedwater Start-un Valve A modification to install a feedwater startuo control valve was connl eted . This modification involved installing a blockinq val ve , control valve, connected piping and control cabling for the operation of the control valve around the MO-2144C reactor feed nump discharce cate valve. The nuroose of this modification is to allow a feed pumn to continuously f eed the reactor vessel
Page 3 O through the control valve rather than through a throttled 1R" gate valve, improving reactor water level control during startun and mininizing thermal cycling in the feedwater nozzles.
Fiqh Pressure Service Water (HSW) Discharge Valve Control A modification to the control circuit for the HPSW discharge valves was completed. This modification involved the deletion of the automatic pressure controller from the control circuit for the HPSW discharge valves (MO-10-99A-B,C,D). The purpose of the controller circuit was to maintain a positive differential pressure between the HPSW system and the RHR system. The controller was replaced with a conventional motor operated valve control with a hand switch in the control room. The purpose of this modification was to replace the automatic control circuit which was a maintenance problem and unnecessary since valves were usually operated in the full open or closed position. Orifices installed in the piping downstream of these valves normally ensure proper pressure differential. Annunciators are installed to alert the operator if proper differential pressure is not maintained such that rapid appropriate corrective action can be taken.
O containment Pressure Transmitters ,
A modification to provide containment pressure instrumentation capable of monitoring containment conditions during the course of an accident was completed. This modification involved the installation of four cuality assured, environmentally and seismically qualified instrument channels to monitor drywell pressure with a range of 5 to 20 psia. The instrument channels are powered from two different power supplies for reliability.
The purpose of this modification was to comoly with NUPEG-0737, Part II.F.1, attachments 4,5 and 6 nroviding drywell pressure instruments capable of monitoring containment conditions during the course of an accident.
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Page d Suppression Pool Water Level Transmitters A modification to replace torus water level transmitters LT 2914 and LT 4805 was completed. This modification involved the installation of two quality assured, environmentally and seismically qualified instrument channels to monitor torus water level with a range of 1 to 20 ft. The instrument channels are powered from different power supplies to assure that control room indication will be available in the event of a single failure.
The purpose of this modification was to comply with NUREG-0737, Part II.F.1, attachments 4,5 adn 6 increasing reliability of torus water level transmitters to ensure proper monitoring during post-accident containment conditions.
Reactor Recirculation Pump (2A and B) Seal Leak Flow Switch A modification to install isolation and eaualizer valves on each seal leak flow switch on the 2A and 2B Reactor Recirculation Pumps was completed. This modification involved installing two 3/4", Mark 130 valves in the isolation lines and a 1/2" Mark 130 valve in the ecualization line of each seal leak flow switch.
The purpose of this modification is to provide for t'esting the flow switches .
Main Steam - Seal Steam Header A modification to replace a portion of the steam seal header supply line was completed. This modification involved replacing the portion of the steam seal header supply line that runs from the 4" tap on the main steam line just upstream of No. 4 MSV to the first isolation valve (5.3). The piping and valve were replaced with O-Listed material. The purpose of this modification was to bring this portion of the supply line into conformance with original design requiremnts.
I Containment Protection Screens For Purce and Vent Valves A modification to install debris protection screens on the containment purge and vent valve. penetrations was completed.
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This modification involved the installation of debris screens on penetrations N-25, N-26, N-205A*, and N-214 The purpose of this modification is to ensure that purge and vent valve closure will not be prevented by debris which would potentially become entrained in the escaping air and gas following a LOCA.
- A debris protection screen was erroneously installed on penetration N-205A (torus vacuur, breaker nine) and will be removed and installed on penetratien N-205R (torus exhaust pipe).
This correction will be reflected in the next Annual Modification Renort.
Long Term Nigrocen Supp1v to ADS Safety / Relief Valve Accummlators A modification to install an alternate, long term nitrogen suppiv to Automatic Depressurization System (ADS) accumulators 256A,B,C,G, and K was completed. This modification involved inta111ng nitrogen supply lines through nenetrations N-47 and N-107 and connecting them to a new, solit-ring header which was installed in containment ~.~~Three ADS valves were connected to one (S section of thi split header while the rehaining two were (s/ connected to the other section of the split header.' The purpose of this modifcation is to provide a seismic, long-term, safety-grade N2 supply to assure ooerability of the ADS valves for a j period of 100 days following an accident (as per NUREG-0737, Item t
II.K.3.28). As a result of this modification, a Technical Soecification chance was required. This change involved the addition of isolation valves to Tables 3.7.1 and 3.7.4 of the Specifications.
Containment High Range Radiation Monitors A modification to install high range containment radiation moni tors was completed. This modification involved the installation of two, quality assured, environmentall y and seismically qualified instrument channels with a range un to IPA R/Hr. This upper range limit is eauivalent to IP7 R/Fr for 60 kev to 3 MeV photons. The instrument channels are assigned to two independent electrical divisions to assure that the control room indication will be available in the event of a sinole failure. The nurpose of this modificaiton is to accuire an O
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indication of the magnitude of radiation release to containment following an accident in order to implement emergency actions.
As a result of this modification, a change to the Techniical Specification Tables 3.2.F and 4.2.F was requested to provide for surveillance testing of these instruments.
Containment Torus Shell Modifications A modification to weld T beam stiffeners on the exterior of the torus shell was completed. This modification involved the installation of 4 circumferential T-shape stiffeners on the exterior of the torus shell in each torus segment. Condensate return and steam supply lines to area unit heaters were relocated to eliminate interference with the stif fner installation. The puroose of this modification is to upgrade the structural integrity of the torus shell and torus support system.
Exterior Torus Penetration Stiffeners A modification to install penetration stiffner nlates around each piping penetration having a diameter of 6 inches or larger was completed. This modification involved the installation of 314" stiffener plates radially around the pine, welded'to the pipe and the torus shell. The puroose of this modification is to reduce stresses caused by torus shell motion due to LOCA and S/RV discharge loads.
Modification of Torus Internal Structures A modification to the structures inside the torus was completed.
This modification included installing stif fener plates at vent header - downcomer intersections, installing stiffener plates at wetwell - drywe11' vacuum breakers, installing new supports on internal discharge pipino at nenetrations N233 and N734, modifying HPCT and RCIC pipe sunports, and modifyino vacuum breaker drain lines. The purnose of this modification is to correct deficiencies identified by the Mark I containment procram by modifying structures inside the torus to resist suppression L (2)
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pool hydrodynamic loads which result from steam blowdown due to a l loss of coolant accident or main steam relief valve discharge.
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i Torus Support Column Tie Down Modification !
A modification to install tie down assemblies at each of the torus support column bases was comoleted. The tynical-tie down assembly consisted of gusset and stiffener plates attached to the suoport columns. The purpose of this modification $ is to prevent the upward movement of the torus when a nressure increase in the suppression chamber occurs during a postulated LOCA or S/RV discharae.
Temporary Penetrations Through Reactor Building Wall A modification to install five-10" and one-9" temporary penetrations in the west wall of the Reactor Buildina was O comleted. The modification involved core horina six temporarv penetrations which were used for welding leads and electrical feeds. These penetrations were sealed during the torus modification work with non-hardening, fire resistant caulking comoound. At the end of the modification work, the core bores were filed with concreted and sealed with cover plates on each side. The purpose of this modification was to f acilitate containment suppression chamber modifications.
Reactor Water Clean Up (RWCU) Suction Line A modification to renlace the RWCU suction line from the connection at the PHR suction line to the drywell nenetration was connleted. This modification involved replacino the RWCU nining (6", Sch. RO , Type 304 stainless steel) from the weldolet at the RHR Suction Line (EL.190") up to and includino the 40 decree ethow at Drvwell Penetration N-14 (EL.178') with 6", Sch. 80, l Type 316L stainless steel pipe. Also, the 46 and MO-15 valves !
were replaced with the refurbished Unit #3 d6 and Mo-15 valves. ;
The purnose of this modification is to reduce the suscentability to intergranular stress corrosion cracking.
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V CRD Scram Discharge Volume Modifications ,
A modification to the Control Rod Drive (CRD) Scram Discharge Volume was completed. This modification involved: replacing the two inch piping between the scram discharge volumes and the instrument volume with six inch piping, installing redundant isolation valves on the discharge volume vent and drain lines, removing relief valve RV-34 on the instrument volume drain line, rerouting the piping for the level detection instrumentation directly to the instrument volume, providing cross connection piping between the discharge volume vent lines, providinc a vent path between the top of the instrument volume and the discharge volume vent system, and providing independent and diverse water level sensing instrumentation by using float switches which were made by different manufacturers. The purpose of this modification is to meet the requirements of: the NRC's safety evaluation for TE Bulletin 90-17, the NRC Generic Safety Evaluation Report "BWR Scram discharge System" dated December 1990, and NUREG-0460, " Anticipated Transient Without Scram,"
paragraoh 2. 3.1.1, part 2 of volume 4. As a result of this modification, a change to the Technical Specification was required. This change involved the addition of the scram discharge volume vent and drain line valves to Pables 3.7.1 and 3 3.7.4.
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Improved Time Delav Relays for Reactor Peed Pump Circuit l
A modification to replace Anastat pneumatic time delay relavs with Acastat electronic time delay relays in the control circuits for the reactor feed numps was completed. This modification involved replacing relays desionated as "EA" and "EC" which are l associated with the reactor feed pump trip on low suction I pressure of 300 psig. The purpose of the modification is to improve the reliability of these components by ensuring that the time delay relays operate or time out correctly after being l called upon following long periods of inoperation.
Tmoroved Time Delay Relays for the Fecirc Motor - Generator Sets A modification to replace the pneumatic relays with more reliable electronic relavs in the control -circuits of the recirculation l
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page 4 motor-generator (MG) sets was comnleted. This modi fication involved removing the Agastat pneumatic time delay relays and installing surface mounted sockets and new Acantate TR electronic time delay relays with locking strans. The recirc MG set relays which were modified included: fluid drive low oil pressure alarm circuitry relays (3 instantaneous time delay relays and 3 time delay relays of 15 seconds each), loss of generator stator cooling trip relav contact (1 sec. for one pump; 10 sec. for second pump), recirc pump breaker lockout auxiliary circuit (10 sec. time delay relay for over current blocking during starting function; instantaneous time delay relay for field breaker control and excitation transfer), emergency tube oil pump auxiliary relays (1 sec. timer which prevents auto-start of AC lube oil pumps on lowering pressure; instantaneous relay which locks the scoop tube when emergency lube oil pumps low pressure),
time delay relay to start emergency lube oil pump (3 time delay relays of 15 sec. each) . The purpose of this modification is to improve the reliability of the recire MG sets by ensuring time delay relays operate on time out correctly after being called unon following long periods of inoperation.
O Improved Time Delav nelays for 4KV Switchgear A modifiction to renlace the pneumatic time delay relays with more reliable electronic relays in the control circuits of tha 4KV emergency buses was completed. This modification involved replacino tha Anastat pneumatic time delav relays with new l
Acastat PR electronic time delay relays for: the Diesel Generator Breaker close circuit 0.5 sec. time delay relav, the breaker backup / transfer 0.25 sec. time delav relay, the ECW punn auto start 22 sec. time delay relay, the ECW nump discharce valve auto open 35 sec. time delav relay, and the emeroency auxiliary switchaear load center transfer 3 sec. time delay relay. The nurpose of this modification is to imnrove the reliability of these components by ensuring that the time delay relays operate after long periods of inoperation.
Improved Time Delay Relays for Diesel Generators A modification to renlace four pneumatic relavs with more reliable electronic relays in the control circuits for the diesel A
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. Page 10 generators was compl eted. This modification involved replacing the Agastat pneumatic time delay relays with new Agastat TR electronic time delay relays with locking straps. The foll owing diesel generator relays were renlaced:: (1) TD-1, 3 min. pre-lube timer relay, (2) TD-2, start failure (lockout) relay, ( 3 ) TD- 3, generator loss of field and field ground alarm relay, and (4) TD-4, shutdown and holding circuit relay. The ouroome of this modification is to improve the reliability of these components by ensuring that the time delay relays operate or time-out correctiv when called upon to operate after long periods of inoperation.
Addition of Reactor Water Level Recorders A modification to add redundant, safety-related, reactor vessel water level recorders to the main control room was completed.
These recorders monitor the reactor water level over the range from normal level to fuel bottom. This modification involved the addition of two safety-related, 0-listed, qualified reactor water level recorders. These recorders were designated LR 2-2-3-73A and LR 2-2-3-728. Each recorder has two channels, o'ne for wide
() range reactor level (-165 to +50 inches) and one fo.r fuel zone level (-325 to 0 inches). These two channels cover the recuired range as recommended in NUREG--0737, " Clarification of TMT Action Plan Requirements.". Each recorder and its associated innut instrumentation is assigned to a senarate electrical division to ensure a sincie failure will not disable both recorders. The purpose of this modification is to meet guidelines of NUREG-0737, Item IT.F.2 for reactor vessel water level to be recorded over the range from normal water level to bottom of fuel.
l Automatic Switchover of RCIC System Suction l A modification to add controls to automatically transfer the RCIC l oumn suction from the condensate storace tank to the suppression 0o01 on low condensate storage tank level was completed. This modification involved addina two condesnate storage tank level instrument loons, each consisting of a transmitter and a trin l unit, and modifying the controls for torus suction valves MO l 34 and MO-13-41. These suction valves will open whenever the l 1evel in the condensate storage tank decreases to five feet above i
the bottom of the tank (or 10,000 gallona left in the tank).
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Page 11 This valve was chosen to dunlicate HPCT autonatic transfer from _
condensate storage tank to the torus. Because this change converted a manually-opened containment isolation valve (i.e.,
MO-13-14) to an automatically-opened valve, the circuit includes a signal to close the valve whenever a RCIC isolation signal or low RCIC steam line pressure signal is present. These signals will also close valve MO-13-39. This modification was designed in accordance with all criteria applicable to the RCTC system.
The purpose of this modification is to meet the requirements of item II.K.3.22 of NUREG-0737, " Clarification of TMI Action Plan Requirements". Unis modifiction resulted in a change to the Technical Specifications. This chance consisted of adding the condesnate storage tank low level trip function / test to Table 3.2.B and Table 4.2.B of the Technical Specification.
Recirculation Pump Seal Pressure Sensing Lines A modification to install restrictino orifices in the seal pressure sensing lines for the recirculation pumps was comnleted.
This modification involved installino 1/4" restricting orifices
() in the 1" seal pressure sensing lines for the recirculation pumns. The purpose of this modi fication is to conniv with FSAR, Suoplement 1, Question 4.10 which requires all 1" instrument lines which penetrate the primary containment and orioinate within the reactor coolant pressure boundary to have 1/4" flow restricting orifices inside primary containment.
Additional Fuses for Containment Atmospheric Control System (CACS) Solenoid valve A modification to install individual fuses in the control circuits for the solenoid coils of CACS isolation valves was completed. This modification involved installing individual 3A fuses in the control circuits for the solenoid coils of the inboard and outboard drywell oxygen analyzer isolation valves:
SV-2671 (A-G), SV-2479 (A-G), and SV-2990. This modification al so involved adding f use bl ocks for SV-2671 (A-G) in the oxygen analyzer control cabinet 20949 and fuse blocks for SV-297R (A-G) and SV-20A0 in Box J75 The purnose of this modification is to allow a failed sol enoid coil to blow its own fuse while keenino the other solenoid valves in service.
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Page 12 EHC System A modification to install two isolation valves between the hydraulic power unit and the turbine front standard main ston valves, control valves and combined intermediate valves was completed. The purpose of this modification is to allow maintenance of these components without shutting down the EHC power unit.
Reactor Building Chilled Water, Turbine Building Chilled Water, and Drvwell Chilled Water Block valves A modification to improve the local leak rate testing of the reactor building chilled water and drywell chilled water systems isolation valves was completed. This modification involved the addition of the following equipment: 1) test connections and block valves to facilitate leak rate testing containment isolation valves MO-2373 and MO-2374 on the RBCW System; 2) test connections and block valves for the local leak rate testing of
- containment isolation valves MO-2200 A&R and MO-2210 A & B on the l DwCW system; 3) air operated valves on the PRCW side of three-way l val ves MO-20245 and MO-2024A(These four new butterfly val ves l provide a leak tight barrier between RnCW and DWCW. The air-l onerated valves will be normally closed and will onen when the three-way valves are signaled to provide RRCW. Samnie connections were nrovided so samnles can be obtained and analyzed to indicate if anv leakage is occurino through the butterfly valves); and 4) air-operated valves on the R9CW side of three-way valves AO-2352 and An-2354 (the oilot solenoid valves which operate the existing three-way valves al so onerate the new valves. Sample connections were also nrovided on this interface). The purpose of this modification is to imnrove the local leak rate testinq RBCW and nWCW system isolation valves and to preclude leakage of contaminated RBCW into the DWCW and TRO4 through the system interfaces. This modification resulted in a chanqe to the Technical Specifications. This change involved the addition of valves MO-2200A&B, MO-2201A&B, MO-2373, MO-2374 on penetrations N-55, 54, 56, 53, 23, and 24 respectively as Primarv l
Containment Testabl e Isolation Val ves to Tabl e 3.7.4 of the Technical Specifications.
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Page 13 Reactor Protection Svstem A modification to the shutdown scram reset interlock circuit of the reactor protection system was completed. This modification involved removing contact 1-2 of relays SA-K18A and SA-K1913 from shutdown scram reset interlock circuits. The purpose of this modification is to ensure correct relay alignment upon restoration of power. This modificat.'on is in response to SIL-344.
'B' Core Soray Sparger A modification to install a General Electric designed and supplied clamp for the "B" core spray sparger. This modification involved installing a clamp on the "B" core spray sparger T-box.
The clamp is two pieces held together and secured to the sparger by four bolts which were crimped after installation. The purpose of this modification is to strengthen the cracked welded seam of the "B" core spray sparger T-box.
Scram Discharge Volume Continuous Water Level Monitorino &
Control Rod Insertion on Low Control Air Header Pressure A modification to remove the Scram Discharge Volume water level monitoring system and the automatic system to initiate control rod insertion on low pressure in the control air header was completed. These systems were recuired as interim measure nrior to the implementation of the long term program to correct design deficiencies in the scram discharge system. The long term progran involved replacing the existing two inch piping between the scram discharge volumes and the instrument volume with larger piping, as was discussed in a previously mentioned modification.
Completion of this long term correction eliminated the need for the systens which were removed. The puroose of this modification was to remove two systen previously installed in compliance with NRC Bulletin 90-17, suppl ement 1.
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Page la Containment Atmosphere Control and Dil ution 9vstems A modification to replace internal circuit assemblies on containment atmosphere control system (CACS) and the containment atmosphere dilution (CAD) system. This modification involved replacing the internal circuit assemblies 444043 on containment pressure transmitters' PT 250AA, PT 250913, and PT4905 in the CACS and CAD systems. The purpose of this modification is to eleminate the grounds on the positive output leg of the emerqency core cooling system power sunplies.
HPCI Turbine Exhaust Drain Pot Val.ve A modification to temporarily replace the HPCI turbine exhaust drain pot valve SV-54 with a manual valve and modify the piping to suit the new valve was completed. The ouroose of this modification is the provide a temporary renlacement for SV-54 since the old valve was not repairable and a renlacement had a 20 week lead time.
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Main Steam T901ation Val ve Drain Val ve A modification to the MSTV drain valve was comoleted. This modification involved installing a strip of stainless steel aoproximately 1/R inch think by 4 innches long on the valve gate wedge. The purpose of this modification is to pronerly position the valve gate in relation to the inbody guides.
Modification of Annunciator Alarms in the Main Control Room l A modification to eliminate, relocate and group together, on a l "fi rst alarm in" basis , selected annunciator alarms in the main control room was completed. This modification invol ved the elimination of the " Main Steam Line Leakace" alarm which was was insensitive for nuantifving a small steam line break. All wirino which provided annuciation was removed. In addition, this modification involved relocating certain alarm windows so that the alarm windows desionated as a "first alarm in" group are annunciated on the same panel . The wirino chances that had to be l
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made to complete this part of the modification were done at the annunciator termination cabinets in the Cabl e Spreading roon.
Lastly, this modification involved groucir.g tocether on a "fi rst alarm in" basis selected alarm windows. To complete this part of the modification, a wiring change was made on each alarm window at the annunciator cabinet in the Control Room. The purpose of this modification is to notify the Control Room operator as to the "first al arm in" condition.
Process comouter Wiring Inout Changes A modification to the process computer analog input points was completed. This modification involved moving the comouter input wires for 15 analog input points directly to the voltage dropping resistors. Previouisly, the internal cabinet wiring included extra lead length which increased the effective resistance about 1%. This modification moved the input wires directly to the resistor terminator strips. The following analog inputs were affected:
(1) Recire Drive Flow (A1, A2, B1, 97) f']
(2)
(3)
Peactor Feedwater Tnlet Plow (A,B,C)
RWCU System Flow (A,B)
(4) Reactor Outlet Steam Plow (9) Reactor Water Level .
(6) Reactor Pressure (7) Reactor Core Dif f erential. Pressure (R) CRD Flow (9) Total JRT Pumo Flow The purpose of this modification is to imorove the accuracy of the process comnuter.
Torus Smoke Detector Alarm System A modification to the torus smoke detector alarm system was completed. This modification involved installing a temporary switch in the torus smoke detector alarm system. The purnose of this modification was to eliminate the f recuent disconnecting and
l Pace 16 reconnecting the alarm when there was welding being done near the smoke detector.
HPCT Gland Seal Condenser A modification to the HPCT oland seal condenser was completed.
This modification involved installing metal bands on the upner and lower joints of the HPCT cland seal condenser shell to bonnet connection. The nurpose of this modification is to eliminate the gasket from being extruded by transient pressures causing gasket failure and was done in accordance with GE SIL No. 129 Process Computer Data Bank tindate A modification to the process comnuter data bank sof tware was completed. This modification involved updating the data arrays to reflect the new core confiouration due to the replacement and
(~)N x- shuffle of fuel bundles, control rods, and LDPP's. ~The purpose of this modification is to modify the TCPEX array to allow accurate tracking of % B-lO depletion and leechina of control blades.
Temporary Neutron Flux Monitorina System A modi fication to install a neutron flux monitorinq system was completed. This modification involved mountina a neutron flux detector and amnlifier inside the drvwell. The detector was sunnended from a cable, restina against the primary shield wall ,
near the core midplane level. The detector was anchored fron below by another cable. An indicator was installed in an accessible location in the reactor buildina. The nurnome of this modification is to determine if an EX-CORE neutron flux monitor would meet the recuirements of Meg. Guide 1.97, " Instrumentation for Licht Water Cooled Muclear Power Plants to Assess Plant and Envi rons conditions During and Following an Accident."
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V RHR Pumn Motor A modification to repair the damaged 2A RPR pump motor was completed. This modification involved repairing the damaged air seal / vent passage area in the upper end shield of the 2A RMR pump motor. This required removing damaged portions of the lands by machining then inserting and pinning a bronze bushing of proper size into each land. The face and I.D. of each bushing were machined to re-establish the original dimensions and configuration of the air seal / vent passage area. This restored the function the air seal. In addition, the oil cover plate was damaged beyond repair. The casting was renlace by a steel plate of the proper dimensions to fit the opening above the oil reservoir. This cover is a splash plate and does not nrovide any structural integrity or leak tight containment pressure boundary.
The purpose of this modification was to repair and put back in service the damaged 2A RHR pump motor.
Reactor Feed Pumn Turbine Trip T,oci c
(~h A modification to temporarily nodify the 2C RFPT trin logic was
\/ comnleted. Thia modification involved addina a I?( VDC time delay relay in the control circuit around pressure switch (PS)-
- 11. PS-11 should have normally closed contacts bpt was renlaced (due to a leaky dianhragn) with a pressure switch with normally open contacts. *he puroose of this modification is to convert PS-11 from normally onen to normally closed status. PS-11 will be replaced with the proper type pressure switch as soon as it becomes available.
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Paqe 1A UNIT 3 Reactor Water Cleanuo System A modification to modify the limitoroue motor onerator switch for the reactor water cleanup valve MO-3-12-15 was completed. This modification involved converting the Limitoraue dual contact switch (SB-2) to a single contact switch (SWB-2). The purpose of this modification is to eliminate the overtorcuing of MO-3-12-15 and scoring the valve seat.
Process Computer Target Exposure Data Rank Revison A modification to the process computer target exposure data bank was completed. The OD 16 program is a fuel management program which is used to predict the future exposure and power distribution in the core during the course of a fuel cycle. The data results, from the program, are used as an aid to determine the rod patterns during the cycle. However, the present process comnuter sof tware model (OD16) has the capability of, handling fuel column length of 144 inches, whereas the three-dimensional
() simulator code, PANACEA, had the canability of handling fuel lengths in excess of 144 inches. Since Peach Bottom Unit 3 contains predominate 1v 150 inch fuel , the dif ference in the model designs resulted in a small error introduced into the Tarcet Exposure Distribution Array (TXR7P) data. To eliminate thin error, this modification involved terminating the PAMACEA code i
target exposures at 144 inches and re-apportioning them into the l 12 axial nodal values used by the process computer. This revised TXR7P and FCEX data resulted in more realistic axial average exnosures. The purpose of this modification was to correct the error into the TXREP in the process computer.
Process Computer Cycle 5 MCPR Limits Revision A modification to the Process Computer data bank was conoleted.
This modfication involved revising the MCPR Limits in accordance with L.*:ense Amendment No. 85 in which the plant is permitted to operate whith less restrictive MCPR limits from BOC up to 1000 MWD /T before End-of-Cycle (EOC) and from 1000 MWD /T hefore EOC to EOC. The purpose of this modification is to revise the MCPP limits to comply with the revised Tech. Spec. MCPR limits.
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Process Comnuter NSSS nD6 Procram Sostware Modi fication A modification to the process computer data bank was completed.
This modification involved revising the Critical Bundle Power Cal cul atior, option of the .NSSS OD6 program. The orogram would edit the critical power data based on the smallest CPR values rather than the hiahest valu'es of MPLCPR (Maximum Fraction of ~
Limiting CPR). The purpose of this modification was to correct a sorting problem with option 3 of the OD6 procram. ,
COMMON Process Computer P1 Format Revision A modification to the process computer was comnieted. This modfication involved I'evising the P1 edit format to replace WitTR with Fraction of Rated Power (FRP). The changes wer'e made to the O OD17 program which generates the periodic nrogram fprmats. The purpose of this modification is to provide the reactor engineers with the fraction of rated powe'r','in particular durina start-un for APRM calibration. .
I Process Computer Sof tware Change to Initialization Procram .
A modification to the initialization (TN7) proqram of.the proces9 computer. This modification involved modifyina the Tu7 nrogran to turn on the LTA proqram during on-line/off-line re-initialization of the process comnuter. Following off-linh -
ini tiali zation, the LTA program was brought if nto the l arge mencry-area and attemp?d to perform its on-line functions (data checks, messace outnuts, etc.). Unabl e to comp'lete the on-line functions, the LTA program remained in the l arge memory area ,
thus nreventing the On 15 program (drum check program) fron entering the large memorv. The nurnose of this modification is to bypass the LTA turn-on software whenever the computer is re-initialized off-line and to. permit the OD 19 proqram to nerform a drum data check.
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pl ant Radio Comm' uni cations
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A modification',to install an improved plant radio communications was completed. This modificationinvolved installing a
'Jdistributed antenna system throug'nout the main clant and diesel buildino consisting of approximately 55 dish-type antennae, in, stalling a radio base station located in U12 turbine building
' fan room.(ELx195'), and connecting the security system base o
stati~nito the distributed antenna system. The purpose of this modification is to provide improvement to the plant radio
. communications system in order to meet the recuirements of the Reg. Guide to 10 CFR73.55_and to improve the saf ety and ef ficiency of plant operations.
s Uni t 1 - Alternate Chemistry and Counting Lab
' A modification to furnish' an alternative chemistry and counting laboratory in Unit I was. completed. This modification involved refurbishing the Unit I chemistrv and counting rooms and
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outfittinq the rooms with laboratory equipment. The' electrical
(,'-) : work con.s.isted of nroviding feeds for the Elcar Lin,e Conditioner, Noc_ lear Data 6650 romnuter, Baird Proportional Counter, Gow Mac Gas Chromatoqraph, and the Reporting Integrator. Also, existing lights and outlets were inspected and repaired. Additionally, manual reset devices were installed on the line conditioner, comouter HVAC, and the proportional counter. These devices are to protect the equipment ~from beinc re-enercized at hich levels if power is temporarily 1 cst in the counting room. The purpose of this modifi' cation is toi provide PBAFS Units 2 and 3 with continuing counting and _ radio-chemistry capabilities in the event of an accident.
Security System Comnuter A modification to the security system computer was completed.
This modification involved installing Sola constant voltace transformers in the power sunnly to the security system computer.
The purnose of this modification is to increase security system reliability by eliminating unnredicted voltace snikes.
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e PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (2:518414000 June 9, 1983 Docket Nos.: 50-277 <
50-278 Mr. J.M. Allan, Acting Administrator Region I Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King o f Prus sia, Pennsylvania 19406
SUBJECT:
Annual Plant Modification Report - 1982 Peach Bottom Atomic Power Station Uni s Nos. 2 and 3
Dear !!r. Allan:
Enclosed are two copics of the 1982 Annual Plant Modification Report for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.
i l This report is being submitted in fulfillment of the reporting requirements of_10 CFR 50.59 describing changes I made to the facility as the facility is described in the final I safety analysis report.
Very truly ours,
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W. M. A en Engineer-in-Charge Licensing Section Nuclear Generation Division WMA:Im I Attachments cc: Document Control Desk i U.S. Nuclear Regulatory Commission Washington, DC 20555
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