ML20043D070

Provides NRC W/Addl Info Re SPDS & Responds to Concerns Raised During 900117 & 18 SPDS Audit Documented in 900130 Ltr

ML20043D070
Person / Time
Site:	Oyster Creek
Issue date:	05/17/1990
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006070091
Download: ML20043D070 (7)

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GPU Nuclear Corporellon W Post Office Bor 388 Route 9 South Forked River, New Jersey 08731 0388 I 609 971 4000 Wnter's Direct Dial Number:

May 17,1990 ,

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I U.S. Nuclear Regulatory Commission Attna Document Control Desk Washington,'D.C. 20555 Dear Sirs ]

1 Subjects Oyster Creek Nuclear Generating Staticn Docket No. 50-219 Additional Information on SPDS

References:

1. NRC Letter to GPUN, 1/30/90 "NRC Findings on SPDS Audit"

2. NRC Letter to GPUN 3/5/86 "SPDS SER" The purpose of this letter is to provide you with additional information concerning our Safety Parameter Display System (SPDS) and to respond to NRC concerns raised as

. a result of the SPDS audit as documented in Reference 1. Attachment I provides the l information requested by the staff during a conference call on Monday, April 16, l 1990. The information describes the steps an operator would take to verify that containment isolation has been achieved.

Attachment II provides responses to each of the NRC concerns raised during the l January _17, 18, 1990 SPDS audit. Based on discussions with the staff, we understand i

( that providing this information should resolve all outstanding issues concerning the  !

oyster Creek SPDS.

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[ If further information is required, please contact Brenda DeMerchant, OC Licensing

. Engineer at (609) 971-4642.

l' Very truly yoursy I' tzpatrick wn/

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l' i President and Director Oyster Creek EEF/BDeM/je '

Enclosure-(ce's on page 2)- ,

9006070091 900517  ;

PDR ADOCK 05000219 GPU N ear Corporation is a subs: diary of General Pubhc Utihtes Corporation [N ,

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cc Mr. Thomas Martin, Administrator j

, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road l King of Prussia, PA 19406 i NRC Resident Inspector Oyster Creek Nuclear Generating Station i Mr. Alexander Dromerick U.S. Nuclear Regulatory Commission i Mail Stop No. P1-137 l Washington, DC 20b55 i

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• - a l- Attachment I at' 1: .

Upon receipt of' containment isolation demand, a Control Room operator will be directed by

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y the css to perform-the following verifications (by physically reporting to the indicated-

'- panel) using Procedure 312 " Reactor Containment Integrity and Atmosphere Controla.

,h < System Valve No. Panel No.

DW Vent / Purge. V-27-1 11F~

' V-27-2 11F Sc V-27-3 11F V-27-4 11F i,; < Torus, Vent V-28-17 11F V-28-18 11F Torus 2"' Vent Bypass V-28-47 11F p.-

DWEDT V-22-1 11F V-22-2 11F j,.

7 DW Floor Sump V-22-28 11F V-22-29 11F V-16-1

' Cleanup 11F V-16-2 11F V-16-14 11F U , V-16-61 11F

' Shutdown Cooling V-17-19 11F V-17-54 11F Torus /Rx Bldg.; V-26-16 11F

, Vacuum. Breakers! V-26-18 11F

. - RBCCW- V-5-147 1F/2F NI V-5-167 1F/2F d[ V-5-166 1F/2F ep  ;**TIP Air /N2 Purge Valve V-23-70 (Four (4) *ndividual

-lTip Drives) 4R 6 .

< N2.' Purge V-23-13 12XR

'l V-23-14 12XR N . V-23-15 12XR V-23-16 12XR

. :1 f: N2 Hakeup V-23-17 12XR j V-23-18 12XR V-23-19 12XR V-23-20 12XR l

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• • The actual valve position cannot be verified anywhere. There is no physical way to

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verify.the actual position of this valve.

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System Valve No.t P_anel No.

DW 2" Vent Bypass V-23-21 12XR V-23-22 12XR

a. Torus 0 2 8"mPl e Valves V-38-22_ 12XR V-38-23 i

., DW 0 2 SamP l e valves- V-38-9 These valves must be monitored V-38-10 at the containment particulate V-38-16 monitor cabinet on the 23' f V-38-17 elevation using a volt meter-

ATTACKMENT II h GPUN believes that the Oyster Creek SPDS meets the regulations outlined in NUREG-0737 as stated in our certification submittal. However, we are planning SPDS enhancements to improve the conciseness and continuousness of the SPDS. Responses to each of the NRC inspection concerns are given below.

CONCERN A separate alarm status monitor is located 90 degrees away from and to the right of the "SPDS" monitor.

REIPONSE GPUN will provide a method of continuous display of critical safety function (CSF) status on the SPDS CRT so that the SPDS user does not have to rely upon the alarm CRT to know that any CSF has changed status. The SPDS display will be enhanced so that CSF status boxes will appear on the message line of all displays on every CRT of the Plant Computer System. This arrangement will provide a continuous display of the current CSF alarm status except for a brief period when an error message may interrupt. Five boxes will be displayed on the bottom line of each CRT, one for each CSP. The presentation of the boxes will be Human Factored with respect to their legends, colors, spacing between boxes, error message interruption, etc. We believe that this enhancement will satisfy the conciseness and continuous display issues. This modification is expected to be completed by the end of the third quarter.

291LCE.EE A separate containment isolation status panel, No. 11F, is located 180 degrees away from and to the left of the alarm status monitor.

RESPONSE

GPUN maintains that panel 11F is not part of the SPDS but rather is part of the existing control room instrumentation used to confirm SPDS indications. NUREG-0737 states that spi?F is used in addition to-the control room instrumentation and serves to aid and augment these instruments.

Further, NUREG-1342 states the operator should not take actions based on SPDS alone.

GPUN's use of the SPDS is consistent with this philosophy. The SPDS users are trained to confirm all SPDS indications with control room indications. Having all of the-containment isolation valves displayed on the SPDS or on panel 11F would not change the user's actions. Therefore, the proximity of panel 11F to tho SPDS or alarm monitor is not a factor, since this panel is not part of the SPDS.

CONCERN Separate containment isolation status indicators for the traversing incore probe drain lines, reactor building component cooling water lines and containment purge and vent lines are located on toe front and back of other panels.

RESPONSE

As described in the previous response, the SPDS users are instructed to confirm all SPDS indications with control room indications. Panel 11F displays a majority of the active containment isolation valves. However, other valves as identified in this concern are located on other panels in the control room. The SPDS user's actions are unchanged by the location of containment isolation valve status indicators in the control room.

i ' Pbh5 2 CONCERN The "SPDS" monitor and the separate alarm status monitor are not_ totally dedicated because non-SPDS displays can be displayed on the monitors.

RESPONSE

The alarm status monitor will be dedicated to displaying plant computer system-

-including SPDS alarms. This monitor dedication-will serve to provide initial

. notification of a SPDS-alarm. Once the user is viewing the SPDS monitor, there will_b61 continuous safety function status' displayed on that monitor.

CONCERN On displays below the main menu, the "SPDS" monitor does not indicate a change

'in' status for the five plant-specific safety functions.

RESPONSE

As previously disu>tted, GPUN has proposed a method for providing continuous status of the five critical safety functions on the SPDS monitor. This will enable the SPDS user to be alerted to changes in safety function status when he is-viewing a SPDS display other than the main menu.

CONCERN The "SPDS" monitor provides only demand rather than containment isolation valve status.

RESPONSE

'GPUN maintains that.the SPDS is not required to monitor the status of all of the.-primary containment isolation valves. This position is supported by the NRC SER.on the Oyster Creek SPDS (Ref. 2) which agrees that containment isolation demand is' acceptable for the SPDS.

When a containment isolation demand is indicated on SPDS', the user would direct-ancoperator to confirm the demand signal and subsequently the completion of containment isolation from conventional control room indications. Even if all of the containment isolation valves were put into SPDS so that containment tisolation status indication could be displayed, the SPDS user's actions would be no different. The user would still have to direct an operator to ccafirm the demand and completion of containment isolation from the control room panel indications. Therefore, we believe that the existing SPDS indicatioe for containment isolation demand is acceptable for achieving the overview function for which the SPDS was intended.

CONCERN From the "SPDS" monitor, panel 11F in the control room does not provide control sf' room personnel with a complete status of all reactor containment isolation

. valves.

-6 RESPONSE As stated in the above response, GPUN mnintains that containment isolation demand is sufficient in achieving the overview function for which the SPDS was intended. Also,' panel 11F is not part of the SPDS and as such would not require a complete status of all containment isolation valves. The SPDS user is trained to confirm all SPDS indications with conventional control room instrumentation.

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4 finally, the user'e actions would not be altered if the status of all of the containment isolation valves was given on panel llF or even an SPDS display.

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