ML20153E113

Provides Notification of Scheduled Changes for Integrated Plan Issue BN-014A, Resolution of Seismic Weak Links, & Discusses Status of 0.0 G weak-link Upgrades

ML20153E113
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/06/1988
From:	Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805090396
Download: ML20153E113 (3)

Text

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May 6, 1988 l

Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - i INTEGRATED PLAN ISSUE BN-014A, RESOLUTION OF SEISMIC T.SSUES, SCHEDULE CHANGE Pursuant to the requirements of the Integrated Plan, we are required to provide written notification to the NKC of schedule changes to NRC initiated Group B issue resolution completion dates at least 30 days prior to the  !

scheduled completion date. Issue SN-014A, Resolution of Seismic Weak Links was scheduled for completion during the 1988 refueling outage and will now be '

completed during the 1989 refueling outage.

Factora that have contributed to not meeting the scheduled completion date aret (1) Required completion of higher plant priority project (s) (eg. Warehouse ,

Modifications), and (2) turnover of personnel (resignation of two eingineers).

Other Integrated Plan projects have also been reassigned in order to meet  ;

their respective completion dates. In doing so, Integrated Plan Issue BN-014A l had been temporarily put on hold, i i

However, the status of the 0.0 g weak-link upgrades is as follows:

1. Provide tip protection for tool cabinets located adjacent to uninterrupti-ble power supplies for the Reactor Depressurization System (RDS) Channels B and D. ,

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- A modification correcting this situation was completed in October 1986.

2. Provide protection for reactor building Pressure Transnitter PT-174 to  :

ensure it cannot be damaged by lead shielding installed nearby. [

1

- Further analysis has shown no modifications are required to protect the i

• ::smitter; therefore, this portion cf the issue resolution is considered [

to be complete. l

3. Provide protection to prevent motor operators from striking adjacent  !

structures / components due to a seismic occurrence. .

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8805090396 880506 PDR ADOCK 05000155 P

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/ Nuclocr Regulctory Commission 2 Big Rock Point Plant Itegrated Plan Issue BN-014A May 6, 1988

a. Emergency condenser outlet valves PO-7053 and MO-7063 r

- Further analysis has shown that no modifications are required to protect the motor operators frte striking adjscent atructures/

components; therefore, this portion of the issue resolution is considered to be complete.

b. Core spray valves MO-7051 and M0-7061

- A seismic evaluation of the main core spray line near the valves is in progress to more accurately predict at what acceleration levels the motor operators might impact adjacent structures. This evalua-tion will provide recommended solution (s) to prevent impact of the notor operators with adjacent structures. ,

c. Backup core spray valvec MO-7070 and MO-7071

- An analysis is to be performed for the design and installation of -

impact bumpers for these valves.

4. Provide protection of enclosure spray valves MO-7064 and MO-7065 and power conduits to MO-7070 and MO-7071 to ensure that they vill not be damaged as a result of the clean-up demineralizer crane (C-9) being rotated into the above items due to a seismic occurrence.

- Analysis is to be performed for the design and installation of a removable ,

rotation prevention mechanism for this crane.

5. Structurally upgrade the vest support column in the outside cable penetra-tion room in order to reduce the east-west amplification values of Coluen EA-8 (ref Dvg 0740020222) and reduce the horizontal displacement of the cable tray floor.

- A detailed seismic analyses for the structural upgrade has been performed i by D'Appolonia Consulting Engineers, Inc (D'Appolonia letter report j dated March 15, 1982). Purther analysis is required for the design of bracing members and connection details.

6. Structurally upgrade existing support frame for enclosure spray actuation Pressure Switches PS-636 and PS-7064 to resist seismic induced forces.

- Additional analysis is required for the design and installation of a nev  !

support frame for the enclosure spray pressure switches.

Overall this project is approximately fifteen percent complete with an estimated 300-400 man-hours required to complete remaining engineering,  ;

fabrication and installation. To complete these projects as scheduled, it is anticipated that an addittorca? 9-12 days would be required to be added to the '

1988 refueling outage. Items L.c. 4 and 5 do not require the plant to be in r

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. Nuciccr Regulctory Conniccion 3 Big Rock Point Plant Itegrated Plan Issue BN-014A May 6, 1988 an outage and will be completed as soon as practicable after the 1988 refueling outage. Items 3.b and 6 require an outage and will be targeted for completion during the 1989 refueling outage.

O-Ra1 R Frisch Senior Licensing Analyst CC Administrator, ReFion III, NRC NRC Resident Inspector - Big Rock Point Plant OC0588-0006-NLO2