ML20195G507
| ML20195G507 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/17/1988 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8806280023 | |
| Download: ML20195G507 (4) | |
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[2 / On3 Fir.1 Nrional Plan, Chicago, Illinois h Commonwealth Edison
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Chicago, Illinois 60690 0767 Address Reply to: Post Office Box 767 v
June 17, 1988 Mr. Thomas E. Murley, Director Office of Huclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Quad Cities Station Units 1 and 2 Detailed Control Room Design Review (DCRDR) Schedule NRC Docket Nos. 50-254 and 50-265 References (a): Teleconference between Ceco (I.M. Johnson, et. al.) and NRR (T. Ross, et.al.) on March 4, 1988 concerning Quad Cities and Dresden DCRDR Modification Schedule.
(b):
R. Auluck letter to D.L. Farrar dated March 9, 1987.
(c):
J.R. Wojnarowski letter to J.A. Zwolinski dated December 29, 1985.
(d):
I.M. Johnson letter to T.E. Murley dated August 25, 1987.
Dear Mr. Murley:
Commonwealth Edison Company (Ceco) has committed to performing modifications which address Human Engineering Discrepancies (HEDs) identified during the Detailed Control Room Design Review (DCRDR) as required by NUREG-0737, Supplement 1.
The need for an extension to the committed implementation dates w6s discussed during the referenced conference call.
The specific Quad Cities HEDs and associated new commitment dates can be found in Attachment,A to this letter. Ceco proposed to change these installation dates, as noted in the i
attachment, due to material procurement difficulties.
It was indicated during the course of the conference call that the installation dates for certain Unit 2 DCRDR HEDs has been changed from the second to the third refueling outage, pending receipt of a formal CECO request, this schedule was considered acceptable by the Staff.
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8806280023 880617 gDR ADOCK 05000254 k)
l T.E. Murley June 17, 1988 l
These changes involve the common-unit diesel generator controls and instrumentation, the diesel generator cooling water pump indication and the separation of multiple annunciator input alarms. All of these projects are classified as Category 1 Level c, which indicates the HED is associated with a safety-related system with relatively minimal impact on plant performance (consequence of human error will not lead to degraded plant safety-system).
The lack of common unit diesel generator control and instrumentation on Unit 2 is presently addressed by station procedure QOP-6600-5. The annunciator 1
issues are related to corrective multi-input annunciator windows which have control panel instrumentation available to determine the specific trouble.
Operators are also trained to utilize annunciator procedures for determining the cause of multi-input alarms.
All other items are Category 2 HEDs, which are not associated with any of the plants engineered safeguard systems or safety features. Therefore, commonwealth Edison believes the revised schedule dates do not constitute concerns important to the safety of the station.
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Unavailability of material has been caused by detailed design requiring significantly more time than originally planned. Therefore, the materials were not ordered according to the original schedule. The revised schedule allows for better integrated modification with the existing plant systems. While prepariel this formal request, Csmmonwealth Edison has identified the need to enek relief from a Category 1 HED commitment pertaining to the RCIC trip throttle valve trips.
i In Reference (b), Quad Cities Station was notified by the NRC to j
provide justification for further delays in implementing previous commitments to resolve this Category 1A HED which raised the following concern:
- When the RCIC trip throttle valve trips, it requires that an operator be dispatched to locally reset it, since remote reset from the Control Room is not provided. The delay involved is considered undesirable.
Methods to resolve this HED were previously provided to the NRC in Reference (c) and approved by NRR in Reference (b).
This included an engineering modification to eliminate false overspeed trips caused by the i
hydraulic oil system which has been completed.
Furthermore, a modification to remove the electrical overspeed trip, which was also causing spurious turbine trips, has been completed.
No overspeed trips have occurred subsequent to the above changes.
When CECO responded to the NRC request to justify further delays in implementation of this HED, CECO committed to completion of an additional modification in Reference (d). This modification included installation of two Of the RCIC turbine trips on the trip throttle valve (e.g., low pump suction pressure and high turbine exhaust pressure).
A motor operator would also be added to RCIC trip throttle valve to allow remote reset capability for these j
two trips.
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O' T.E. Murley June 17, 1988 f
However, further review of this additional commitment indicates that the intent of this HED had been satisifed with previously installed modifica-tions.
Installation of the electrical RCIC trips on the trip throttle valve is not a requirement of this HED and the motor operator is only being installed to provide remote reset capability of these two electrical trips. As a result, Ceco believes that the modification to add electrical trips with remote reaet capability to the RCIC trip throttle valve is not an HED commitment but rather a system enhancement and this does not require installation in the current Unit 2 outage.
Please contact this office if you should request further informati7n regarding this matter.
Very truly you s
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I. M. Johnso Nuclear Licensing Adm istrator IMJ/Im Attachment cc:
A.B. Davis - Regional Admin. (RIII)
T. Ross - NRR NRC Resident Inspector - Quad Cities L
4803K
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At t adw(nt 4 Qu.id Citics Units 1 E 2 DCWDR khedule HlO f reien Desc rigli,orj
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Cate2og Maiifica[ inn #
Originnt Cmaitent inclewntation Cuman unit Dieset 0271, 0436 1C M4-1/2 8/ 22 02 2nd Refuetitu outage
- 01-2rd Refuet ing outage
- Generator Dieset Gene-rator Coot irn 0418 1C M4 1/2-87-22 02-2rw1 Refueling Outage
- Q1-2rm1 Refueting Outage
- Water N p Indicatlon, Unit 2 only Annunciator System:
fta mrate Adjustment, 0020 2C M4-2 87 51 cI-2rd Ref ueling Outage c2-3rd Refueling Outage R ingt>ack 0015, 0u16 2C M4-2 87-51 02 2nd Refucting Outage 02-3rd Refueling Outage Reftash 0027, 0074 1C M? 87-51 02-2rd Ref ueling Outage 02 3rd Refuctirn Outage Aujitor y Coding, 0017, 0523 2C M4-2 87-51 02 2rd Refuelits Outage 02-3rd Ref ueling outage feedsater Regulator 02L5 2A M4 87-62 02 2rd Ref ueling outage 02 3rd Refueling outage Isoli, tion valves, l
Unit 2 onty Control of CED Discharge 0176, 0406 28 M4 87-61 G2-2rd Ref ueling Outage 02-3rd Refueling Outage Valve, Unit 2 only Plant Pagiro overido 0102 2C M4-1-87 62 42-2rd Refueling Outage 12/30/88 (Norroutage related)
- Clarifies bhich Unit Outage for Cumon Modifications l
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