ML20205C378
| ML20205C378 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/07/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton, Tam P Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM 2NRC-6-080, 2NRC-6-80, TAC-62924, NUDOCS 8608120318 | |
| Download: ML20205C378 (4) | |
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- o. 2 Unit Project Organization Telecopy ( 2 64 Ext.160 P.o. Box 328 August 7, 1986 Shippingport, PA 15077 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 j
ATTENTION: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 S.E.R Confirmatory Issue 41a Gentlemen:
Attached is a preliminary response to the subject confirmatory issue.
Since information necessary to evaluate the safety injection system (for other than recircul ation mode) and the radiation monitoring systen is i
incomplete at this time, they are not discussed in this response.
It is j
expected that these systens will be discussed by 90 days prior to the fuel 1
loading.
DUQUESNE LIGHT COMPANY By
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V41/ J. Carey Vice President GLB/ijr NR/- ' FIRM /ISSU AR Attachments cc:
Mr. W. Troskoski, Senior Resident Inspector (w/ attachments)
Mr. L. Prividy, Resident Inspector (w/ attachments)
I 8608120318 860807 0
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Onited States Nuclear Regulatory Commission Mr. Harold R. Denton, Director S.E.R Confirmatory Issue 41a Page 3 CC n3NWEALTH OF PENNSYLVANIA )
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COUNTY OF BEAVER
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On this day of
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/h, before me, a Notary Public in and for said Commo$ wealth and County, personally appeared J. J. Carey, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (c.) he is duly authorized to execute and file t
the foregoing Submittal on behalf of said Company, and (3) the statenents set forth in the Submittal are true and correct to the best of his knowledge.
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SHittA U. FAnditE, t!0iArtY PUBUC SHl/PlMPORT 8020, BEAVER C001HY EY COM' IS$iO4 EIPIRES OCf. 23,1989 J
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RESPONSE TO CONFIRMATORY ISSUE 41a SER Excerpt:
Regarding NUREG-737 Iten III.D.l.1, the applicant has not adequately addressed his program and related procedures aimed at minimizing reactor coolant leakage outside the containment.
As a confinnatory iten, the applicant should inlcude with the PGP package a description of this progran identifying the operational and maintenance activities enforced on specified systems to minimize (prevent) postaccident reactor coolant leakage outside the containment.
Response
Leak tests will be perfomed periodically on the following systens which have flowpaths outside containment and which may be used to mitigate an accident, thus having the potential to contain highly radioactive fluids i
or gases:
- 1) Safety Injection (Recirculation Mode) - each refueling
- 2) Recirculation Spray (Containment Depressurization) - each refueling
- 4) Containment Vacuun and Leakage Monitoring -Type A leak test, approximately every 40 months The leak tests will detennine, measure and report leak rates from the above systens.
Procedures to perform these tests are in preparation and will define the methods and equipment to be used to identify leaks and detemine leakage rates.
Corrective measures taken to reduce or eliminate identified leakage will be controlled by the BVPS-2 maintenance progran.
Operator training and adherence to administrative and operating procedures should i
preclude systen misalignment and improper leakage paths.
The following systems are not included in the leakage reduction pro-gran specified by NUREG 0737,111.D.1.1 for the reasons noted:
i
- 1) Chemical and Volume Control (CHS)
Reason: Normal letdown is isolated inside contaiment by Contaiment Isolation Phase A Signal (CIA).
Reactor coolant pump seal water supply will be manually closed by the control roon operator for long-tem contaiment isolation. 2CHS*FCV160 and 2CHS*HCV142 are not required to have a containment isolation signal since they are i
maintained administrative 1y closed durir.g normal operation.
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- 2) Reactor Plant Vents and Drains Reason: The containment sunp, primary drain transfer punp discharge and gaseous releases are isolated by CIA.
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- 3) Post Accident Sampling l
Reason: This systen is isolated by CIA and is only opened for sampling / monitoring during DBA.
- 4) Primary Plant Sampling System Reason: The following samples are isolated by CIA - cold leg, hot leg, pressurizer liquid space, pressurizer vapor space, pressurizer relief tank gas, safety injection l
accumul ator, and residual heat removal heat exchanger inlet and outlet.
Blowdown sampling is a closed system.
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- 5) Containment Purge Reason: During nonnal operation this system is maintained admin-istratively closed and is only opened during cold shutdown and refueling.
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- 6) Gas Supply Reason: This systen is isolated by CIA.
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- 7) Containment Vacuum and Leakage Monitoring Reason: Reactor containment vacuum is isolated by CIA.
- 8) Reactor Coolant System Reason: This systen is inside containment except for RVLIS which has hydraulic isolation devices and is used during acci-dent conditions.
- 9) Area Ventilation Reason: A separate air supply is provided in the control room if an accident occurs.
- 10) Boron Recovery (BRS)
Reason: This systen is not normally used for letdown and is connected to reactor plant vents and drains.
- 11) Residual Heat Removal (RHS)
Reason: This systen is inside containment.
- 12) Gaseous Waste (GWS)
I Reason: This systen is connected to BRS.
When CHS remains isolated, GWS will not be in use.
- 13) Liquid Waste (LWS)
Reason: This systen is connected to vent and drain systens which have no flow path from containment.
- 14) Solid Waste / Decontamination Reason: This systen is connected to CHS, BRS, LWS and the fuel
- pool, and cross-connects to BVPS-1 Solid Waste.
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