ML17277B173
| ML17277B173 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/09/1983 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| GO2-83-1133, NUDOCS 8312190066 | |
| Download: ML17277B173 (12) | |
Text
~j REGULATORY ORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR;8312190066, DOC ~ DATE: 83/12/Q9 NOTARIZED:. NO
- DOCKET
.FAOIL:50 397 WPPSS Nuclear Projectr Unit 2i Washington Public Powe 05000397
'AUTH BYNAME AUTHDR AFFILIATION SORENSENrGBC, Washington Public Power Supply System
~RECIP ~ NAME'ECIPIENT AFFILIATION SCHWENCERrA ~
Licensing Branch 2
SUBJECT! Forwards clarification of responses to NRC Question 423,041 re FSAR Chapter'0 subsections=
on load testingiver ification 8 solid radwaste'sys, r
DISTRIBUTION CODE:
BOOIS COPIES RECEIVEDtLTR t.'NCL Jr SIZE:
' Z TITLE:= Licensing Submittali,PSAR/FSAR Amdts 8 Related CorrespondenceNOTES:
RECIPIENT ID CODE/NAME NRR/DL/ADL NRR L82 LA INTERNAL: ELD/HDS2 IE/DEPER/EPB 36 IE/OEQA/QAB 21-NRR/OE/CEB ij NRR/OE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/OHFS/HFE840 NRA/DHFS/PSRB NRA/DSI/AEB 26 NRR/DSI/CPB i 0 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23 RGA5 EXTERNALS ACRS DMB/DSS (AMDTS)
LPDR 03 NSIC 05 tCOPIES LTTR ENCL 0
1 0
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3 3
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3-3 6
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1 REC IP IENT ID CODE/NAME NRR LB2 BC
- AULUCKBR, 01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE'/SGEB 25 NRR/DHFS/LQB 32'RR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DSI/METB 12'RR DS /RAB 22 E'G FIL 04 AMI/MI8 BNL(AMDTS ONLY)
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1 TOTAL NUMBER OF COP IES REQUIRED; LTTR 53 ENCL 46
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Washington Public Power Supply System P.O. Box 96B 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 December 9, 1983 G02-83-1133 Docket No.
50-397 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 831219OO66 831209 PDR ADOCK 05000397 PDR
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO.
2
RESPONSE
TO QUESTION 423.041 As informally requested by the NRC, the following information is provided by revised FSAR text, supplying clarification of responses to the subject NRC question.
Should you have any further questions, please contact Mr. P. L. Powell,
- Manager, WNP-2 Licensing.
Very truly yours, G.
C. Sorensen, Manager Regulatory Programs SIS/tmh Attachment cc:
R Auluck -
NRC WS Chin BPA AD Toth NRC Site
h pi J
MNP-2 STATUS THROUGH AMENONENT 31 423.041 a.
FSAR Subsection 14.2.12.1.37 has not been modified to include load testing and monitoring of untested buses for voltage.
b.7 FSAR Subsection 14.2. 12. 1.48 has not been modified to include verification of 1) pumps NPSH and lack of vortexing, and 2) proper.operation of basin siphon crossconnection.
b.g FSAR Subsection 14.2.12. 1. 17 has not been modified to include the design requirement that the end product of the solid radwaste system must be free standing and contain no free liquid.
c.
A test abstract for the control air system has not been included in FSAR Chapter 14.
T~ agaCem m noC aa(My aerated, Xkece$ oee,, M +ALL not be, ~needed.
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WNP-2 AMENDMENT NO.
34 January 1984 Signals for these tests shall be simulated from the actual initiating devices when this is practical.
4.
Testing of the Diesel Generators will include the following:
a)
Sequent'ial loading of each diesel gener-ator unit.
b)
Maintenance of specified frequency and voltage during the loading sequence.
c)
The diesel generator's capability to reject and restart their largest single load anytime after the design loading sequence is complete.
d)
The diesel generator's capability to Supply power to vital equipment during loss of station normal power conditions.
Response
to 5.
Electrical separation will be verifed during testing by:
a)
Verifying that operation of the Division/equipment being tested and the non actuation of de-energized buses/
equipment does not affect the proper operation of the remaining buses/
equipment.
b)
Monitoring of the major distribution buses to ensure obsence of voltage.
Main power transformers supplying power from the off site system cannot be full load tested, they are testing per this procedure to the design emergency load.
All other in-plant power sources are load tested in their individual preoper-ational tests.
14.2.12.1.38 DELETED 14.2.12.1.39 DELETED 14.2.12.1.40 DELETED 14.2-71
c
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WNP-2 AMENDMENT NO.
34 January 1984 c ~
General Test Methods and Acce tance Criteria Standby Service Water System heat dissipation capabilities are not demonstrated during the preoperational test.
Verification of this sys-tem is demonstrated by the proper integrated operation and performance of the following:
l.
Pumps and related controls 2.
Remote-operated valves and controls 3.
Automatic-operated valves and control logic 4.
.Instrumentation 5.
Annunciators 6.
Standby Service Water System control logic response to a simulated loss of normal station power event.
Response
to b-.7.
7.
Pumps NPSH adequate and no vortexing.
8.
Proper operation of basin siphon crossconnection.
l4.2.l2.l.49 Plant Communications System Preoperational Test a ~
~Pur ose To demonstrate that the Plant Communciations and Evacuation Alarm System will provide effective communication between various plant locations and to verify proper operation of the emergency evacuation alarm components and system.
The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Test and Startup Manager has approved the initiation of testing.
c ~
General Test Methods and Acce tance Criteria Proper operation of all the communication system components and the emergency evacuation alarm system and components will be demonstrated.
l4.2-78
4 A ~
WNP-2 AMENDMENT NO.
34 January 1984 c ~
General Test Methods and Acceptance Criteria Responss to b;-9 Testing will demonstrate that the pumps,
- tanks, controls and valves including automatic isola-tion, diversion and protective features and instrumentation and alarms will operate and function in accordance with design requirements.
Testing will also verify that the WNP-2 Process Control Program results in an acceptable waste form as required by 10CFR61.
Simulated waste will be verified to form a free-standing mono-lithic solid with no free liquid prior to imple-mentation of the solidification process on radioactive waste.
Liners containing solidified waste will be inspected prior to shipment to the disposal site to verify compliance with 10CFR61 requirements.
14.2.12.1.18 Reactor Protection System Preoperational Test
~Pur oee To veri fy the proper operation of the Reactor Protection Sytem (RPS),
including sensor logic and their respective scram relays, scram reset time delay, the annunciators, and motor-genera-tor set power supply.
The System Lineup Tests have been completed and the TWG has reviewed and approved the procedure and the Test and Startup Manager has approved the initiation of testing.
c ~
General Test Methods and Acce tance Criteria Verification of the RPS capability is demon-strated by the proper integrated operation of the following:
1.. Motor-generator set performance 2.
Sensor logic and scram relay logic 3.
Scram reset time delay 14.2-54
4
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