ML20215L591

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Forwards Addl Info on Control Room Isolation on Radiation, SER Confirmatory Item 46,per .Response Delayed Until All Five Info Requests Fulfilled.Ser Confirmatory Item 46 Can Be Closed
ML20215L591
Person / Time
Site: Beaver Valley
Issue date: 10/16/1986
From: Carey J
DUQUESNE LIGHT CO.
To: Harold Denton, Tam P
Office of Nuclear Reactor Regulation
References
2NRC-6-108, TAC-62933, NUDOCS 8610290139
Download: ML20215L591 (6)


Text

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        $VL "9df M                                                                         2NRC-6-108 Beaver Valley No. 2 Unit Project Organization                       Telecopy ( 1 ) 64   Ext.160
          $ s'ox"$2                                                              Oct. 16, 1986 Shippingport, PA 15077 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:        Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear "eactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Additional Infonnation Related to Control Room Isolation Confirmatory Item No. 46

Reference:

A) NRC letter, dated May 23, 1986 l Gentlemen: Attachment 1 provides additional information on control room iso-lation on radiation for Beaver Valley Unit No. 2 as requested by Reference A. The Duquesne Light Company response was delayed until all five infor-mation rquests could be fulfilled. With the enclosed information, Duquesne Light believes that SER confirmatory Item 46 can now be closed. DUQUESNE LIGHT COMPANY By // (d Carey V' W.VFc/ Sr. e President RWF/ijr NR/CNFRM/ITM/46 Attachments cc: Mr. Peter Tam, Project Manager (w/a) Mr. J. Beall, NRC Senior Resident Inspector (w/a) BO[ gp Mr. L. Prividy, NRC Resident Inspector (w/a) 0 y ff 8610290139 861016 {DR ADOCK 05000412 PDR

t ATTACHMENT 1 Beaver Valley Unit 2 Request For Additional Information Related To Control Room Isolation on High Radiation

1. Written confirmation that the applicant will modify the design to eliminate all test switches simil ar to switch "2-6125" shown on Drawing 12241-E-11JP-SH-1 which could be used to bypass or render inoperable the portion of the system associated with inputs from the radiation monitors.

Response

ACN 0-0068 was initiated which will eliminate all test switches which could be used to bypass or render inoperable the portion of the sys-tem associated with inputs from the radiation monitors on Diagrans E-11LL, E-60Q-SH-3, and E-11JP-SH-1

2. Provide detailed schematics which show the contact development for radiation monitors 2RMC*2Q201 and 202.
,       3. Provide detailed schematics which show the contact development for all control switches (such as "1-HVCAD") associated with the control
           -room isolation.

Response: The following drawings are attached: Drawings: GA 0390-4320, Rev. B (attached) SWEC E-11JP-SH-1, Rev. 3 SWEC E-11JP-SH-2, Rev. 3 SWEC E-3, Rev. 12 SWEC E-3K, Rev. 9 SWEC E-3N, Rev. 15 SWEC E-11LL, Rev. 3 SWEC E-6UQ-SH-1, Rev. 10 SWEC E-6UQ-SH-2, Rev. 10 SWEC E-6UQ-SH-3, Rev. 10 SWEC E-6JD, Rev. 9 SWEC E-6JE, Rev. 5 SWEC E-GHF, Rev. 9

4. Since our review indicates that draft revisions to FSAR Chapter 7

, logic diagrans (Figure 7.2-1, Sheet 8 and 7.3-13) provided in the applicant's April 1, 1986, letter do not agree with the detailed schematics provided thus far for our review, provide either correct logic di ag r ams and/or detailed schematics to eliminate this conflict.

Response

Revised drawings attached.

5. Our review indicates that Drawing 11700-RE-21ML-3 does not reflect the design changes related to the interface between Unit 1 control room isolation and Unit 2 control room isolation circuitry. Provide a detailed schematic or later revision to Drawing 11700-RE-21ML-3 which shows this interface.

Response

The NRC requested drawing 11700-RE-21ML-3 during the ICSB site visit in May,1986. Although DLC was able to provide the drawing to the NRC on the last day of their visit, DLC informally had indicated that the drawing was unreviewed with respect to the subject control room isolation on radiation. The subject drawing depicts Beaver Valley Unit No.1 (BVPS-1) systems and was not marked up at the time of the ICSB site visit to show the intended control room isolation changes. BVPS-1 Design Change Package (DCP) No. 711 describes the changes to implement control room isolation on radiation for the BVPS-1 systems. Because BVPS-1 was in a refueling outage, and the new control room isolation changes (required as a result of BVPS-2 ) were not being installed during the current outage, the development of DCP No. 711 by the BVPS-1 staff was not a priority issue. Drawing 11700-RE-21ML-3 has now been marked up to show the intended changes to the BVPS-1 system and is attached. Although these changes are draf t, no additional changes are currently being considered. The final BVPS-1 modifications will be installed before receipt of the operating license for BVPS-2. A final revised as-built drawing will not be available from the BVPS-1 organization until the system is completely installed.

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