ML20077E709
| ML20077E709 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/19/1983 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20077E702 | List: |
| References | |
| NUDOCS 8307280404 | |
| Download: ML20077E709 (10) | |
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Report of Changes, Tests, and Experiments Performed at Pilgrim Nuclear Power Station The following changes and tests were performed at the Pilgrim Nuclear Power Station between July 1,1982 and January 21, 1983, under the authorization of 10CFR50.59(a).
No experiments were performed at the Pilgrim Nuclear Power Station during this period. For each change or test reported below, the statement that it does not involve an unreviewed safety question indicates that the change or test was reviewed prior to implementation and that it was deternined that:
1.
The change or test would not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; 2.
The change or test would not create c possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report; and 3.
The change or test would not reduce the margin of safety as defined in the basis for any technical specification, I
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8307280404 830719 PDR ADOCK 05000293 R
I PLANT CHANGES PDCR 78-42 Area Rad Monitors This PDCR provided area radiation monitors with remote readout capabilities in the radwaste control room for the spent resin, flatbed filter liners, and radwaste demineralizer areas.
Ref. FSAR Section 7.13.5 Safety Evaluation No. 595 This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 78-45 TIP Room Area Rad Monitors This PDCR added a local area radiation monitoring system to the Traversing Incore Probe (TIP) room and the Condensate Regenera-tion room.
Ref. FSAR Section 7.13.5 Safety Evaluation No. 79-SE-01 This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 79-M-08 Instrument and Control Lab Mods Due to an increase in staff and equipment, additional space was needed. This change relocated storage of some I&C equipment, redesigned the present lab, and created a smaller lab for additional space.
(Note:
This PDCR has been superseded and the lab relocated in preparation for the new Administration l
Building presently under construction).
Ref. FSAR Section 12.1 Safety Evaluation No. 79-SE-16 This change does not involve an unreviewed safety question as t
defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 79-27F A0G Information Retrieval This PDCR provided on demand nonttoring of various Augmented Off Gas (A0G) system activities in the Main Control Room.
Through the installation of thermocouples, steam flow trans-mitters and various electronics, the control room operators are now able to monitor steam conditions prior to entry to the A0G system and various in-system conditions previously monitored from the recombiner area.
Ref. FSAR Section 9.4.4.1.6 Safety Evaluation No. 80-PSG-2 l
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This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 79-59 Torus Level Monitoring To fulfill the requirements of NUREG-0578, two channels of redundant level instrumentation capable of monitoring the torus level were added.
Ref. FSAR Section T-5.2a3 Safety Evaluation No. 1008 This change doas not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 80-58 Installation of EOF CcMunication This PDCR is one of several which incorporated modifications due to TMI. The governing documents for the work covered by this PDCR are NUREG 0660 "NRC Action Plan Developed as a Result of the TMI-2 Accident" and NUREG 0696 " Functional Criteria for Emergency Response Facilities."
Modifications covered by this PDCR include, circuitry to trans-mit meteorological data to the E0F, communications (including additional land lines to Civil Defense Centers), Emergency power, security devices (incpding alarms, forces and outside lighting) and fire detectors.
Ref. FSAR Section Appendix P Safety Evaluation No.1047 This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
I PDCR 81-04C Torus Modifications (Monorail)
This change removed the monorail and it's supports from the Torus compartment and placed in storage in the Torus room.
This modification conforms to NRC Acceptance Criteria, Appendix l
A to NUREG-0661.
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Ref. FSAR Section Figures 12.1-13, 15 l
Safety Evaluation No. 1127 This change does not involve an unreviewed safety question as i
i dgfined in 10CFR50.59(a) or a change to a technical specifica-tion.
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PDCR 81-16 Control Rod Drive Temp. Recorder The original temperature recorder (Leeds A Northrup) was worn out and obsolete.
It was replaced with a Kaye Instrument, ell solid state data logger.
Ref. FSAR Section Table 7.7-1 Safety Evaluation No. 1117 This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
PDCR 81-46 HPCI Turbine Ramp Generator This change replaces the " anti-wind up" circuits in the HPCI flow controller loop with a " ramp generator" module in the turbine control system.
All equipment and material are safety-related. The equipment purchased for this change has been accepted as qualified to IEEE-323-1974 and IEEE-344-1975.
Ref. FSAR Section Figure 7.4-5 Safety Evaluation No. 1318 This change does not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-
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The following PDCR's (79-24 Series), modified hangers and supports in various locations, in response to IE Bulletin 79-14 Reference FSAR Sections 2.5.3 and 12.2.3.5.2 These changes do not involve an unreviewed safety question as defined in 10CFR-50.59(a) or a change to a technical specification.
PDCR No.
Safety Evaluation No.
Hanger / Mark No.79-24A 672 H-30-1-41-SG H-30-1-41-SR H-30-1-44-SG 79-24-F.3 739 H-26-1-135 79-24-K.12 1222 H-30-1-92 H-30-1-6SS H-30-1-80 H-30-1-109 H-30-1-111SR H-30-1-138 79-24-N.11 1193 H-30-1-357 H-30-1-66SS H-30-1-328 H-30-1-286 H-30-1-308 H-30-1-369 79-24-T.6 1153 H-30-1-296 H-30-1-317 H-30-1-58SA H-30-1-340 H-30-1-SA3 H-30-1-64SA l
H-30-1-355 H-30-1-367 79-24-XE.12 931 H-30-1-114S9 H-30-1-22SG l
79-24-XE.13 961 H-30-1-10SS 79-24-XE.15 988 H-26-1-194 79-24-XE.16 993 H-30-1-110 79-24-XE.17 931 H-30-1-58 H-30-1-113 H-30-1-142 H-30-1-72 H-30-55SG l
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PDCR No.
Safety Evaluation No.
Hanger / Mark No.
79-24-XF.1 798 H-30-1-238 79-24-XF.2 821 H-30-1-171 H-30-1-175 H-30-1-174 79-24-XF.3 830 H-30-1-SA-6 H-30-1-104SA H-30-1-96SA 79-24-XF.4 844 H-14-1-34 79-24-XF.5 857 H-30-1-1219 79-24-XF.6 875 H-30-1-239
I 79-24-XF.7 878 H-14-l'-33 79-24-XF.8 893 H-14-1-1221 79-24-XF.9 933 H-30-1-1218 79-24-XF.10 980 H-30-1-173 79-24-XG.1 813 H-10-1-129 79-24-XH.1 866 H-19-1-SA e
79-24-XJ.1 837 H-5-1-59 H-1-1-1210
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79-24-XJ.2 861 H-6-1-66 FG-1-15R FG-1-14,R H-6-1 61 79-24-XJ.3 868 FG-1-13R FG-1-12R I
79-24-XJ.4 882 H-6-1-64 79-24-XJ.5 939 H-6-1-58 l
F-6-1-10R 79-24-XJ.6 955
- F-6-1-11R 79-24-Y.13 872 H-30-1-60SR H-30-1-73SH H-30-1-376 l
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r The following PDCR's (81-53 Series)a modified masonary walls in various locations, in response tc IF Bulletin 80-11.
t Reference FSAR Se$tions 12.2
'Thest changes do not involve an unreviewed safety question as defined in 10CFR-50.59(a) or a change to a technical specification.
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PDCR No.
Safety Evaluation No.
Wall No.
81-53-AB.'1 1285 < '
185.2S 81-53-AB.2 1307 185.11 EAW
-s1-53-AC.3 1323
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188.9 NAS 188.11 EAW SI-53-RB.13 1327 65.25
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81.53-RB.4
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1242 64.13 N&S I
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J 81-5,3[RC.3 1265 68.2.N 68.1 EAW
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68.4 N 68.3 N
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.,81-53 0C'.'$
1275 66.11 N&S 66.12 N&S
-e 66.18 E&W 68.0 N&S
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81-53,TB.3 '
1313 209.'8 NAS
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81-53eTD.3. ' /
1316 2162EAW
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. 7-81-53 hA-3 f 1284 191.55 N&S f
4 191.56 E&W
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' 81-53-W A.'5 1306
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191.35 S
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81-5'3-W3',5 1332 191.25 EAW
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191.46 W 81-53-WA.7 1326 81-53-WA.8
$29 191.49 E&W
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81-53-WC.1 1283, f, 194.20 N&S 194.23 S 81-53-WC.2 r1303 81-53-WC.3
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~a,0 194.24 N&S
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g PDCR !!d.
Safety Evaluation No.
Wall No.
. 81-53-WC.4 1325 194.22 E&W 81-53-WC.5 1333 194.21 EAW s
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PLANT TESTS TP-82-25 To monitor performance of the SSW system and RBCCW Heat Exchanger to assure that each operable loop of the SSW system can achieve a cooling capability equivalent to 5000 GPM flow at 65*F inlet SSW tempe ature through the respective RRCCW Heat Exchanger with the associated TBCCW Heat Exchanger throttled. This test will also be user 2 to develop precedural guidance for backwashing anc cleaning RBCCW Heat Exchangers.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
TP-82-32 The purpose of this procedure is to safely checkout and test the installation end operatica of the new law level Raddaste drur-type compactor, prior to turnover to Waste Management.
This test did not involve an unreviewed safety question as defined in it)CFR50.59(a) or a change te a technical specifica-l tion.
The curpose of this procedure is the deteWnatior of the exis-tence of air pockets in the Reactor Water te'.el instruments and asn cirted piping.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a tecnnical specifica-tion.
TP-82-42 The new B cordensate pump is one of the unit 2 pumps modified by the manufacturer for use on unit one. The motor on the pump is the original motor for the old R condensate pump.
Since this is not an in kind replacement and the calculated pump curve is shaped differently than the curves generated for A and C condensate pumps, special care must be exercised until B condensate pumps characteristics, and its ability to run in parallel with the existing pumps, are demonstrated.
The purpose of this procedure is to provide guidance for the initial start-up and testing of B condensate pump.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
TP-82-45 To provide a detailed instruction for operating personnel to perform a flow and integrity test of the off-site shipment line integrity using condensate transfer system.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
TP-82-51 The purpose of this procedure is to collect data concerning the reactor water level instrumentation during startup of the reactor.
This test did not involve an unreviewed safety questien as defined in 10CFR53.59(a) or a change to a tec11ical specifics-tico.
To-82-53 To provide 3 metnce far pecylas.?dninistrat6vely, 954 system operability in a nanaca more (cnsistent with tne FSAR Heat Removal Criteria. T51T r.riterie of Secticq VI requires that a S$W Loop deliver 5000 gpm flow 5t an intet temperature of 65 F (equivalent).
This test did not involve an uns tvirded ' safety question as defined in 10CFas0. 59(a) or a change to a technical specifica-tion.
TP-82-?S To provide instauttio..i for perfuraJ ng an UCic system oper-ability test with eeecto cressure < 250 prig.
This test dit not irwolve an vareviewed safety ouestion as defined in 10CFR50.59(a) ar 3 cnange to a tecn*1 cal specifica-tion.
TP-82-30 To provide a detailed instructions for station perscnnel to perform a test to deter.nine possible effects cn reactor water conductivity and main steam line radiation when CR0 system suction is transferred from condensate feedwater header to the condensate storage tank.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
TP-82-5 A test which will assist in diagnosing the movement problems being encountered with control rods as well as attempting to move the rods out to position 48.
This test did not involve an unreviewed safety question as defined in 10CFR50.59(a) or a change to a technical specifica-tion.
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