ML20155C900

From kanterella
Jump to navigation Jump to search
Responds to Generic SER on Seismic Qualification Util Group Resolution of USI A-46 W/Requirements of Generic Ltr 87-02. Completion of Rev 2 to Generic Implementation Procedure Expected in Spring 1989
ML20155C900
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/30/1988
From: Berry K
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 8810100261
Download: ML20155C900 (5)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

o

@. Consumers P0iver -

Kenneth W Berry My Dorenor y y Nwirer Ikemung General Offices 1945 West Pamell Roed. Jeckson MI 49201 * (517) 788 1636 September 30, 1988 Nuclear Regulatory Commission Document control Desk Washington, DC 20$$$

DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

RESPONSE TO GENERIC SER ON SQUG RESOLUTION OF UNRESOLVED SAFETY ISSUE A-46 On July 29, 1988, the NRC Staff issued a Safety Evaluation Report (SER) on Revision 0 of the Generic Implementation Procedure (CIP) for Seismic Verification of Nuclear Plant Equipment developed by the Seismic Qualification Utility Group (SQUG). The letter to SQUG enclosing the SER requests that SQUG member utilities provide to the NRC, within 60 days, a schedule for implementing the GIP. This letter responds to the NRC request for our plant-specific seismic verification plans for the Big Rock Point Plant consistent with the requirements of Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors.

Unresolved Safety Issue (USI) A-46."

An members of SQUG, we have supported the many efforts on which the GIP is based. The SER endorses the methodology and criteria embodied in Revision 0 )

of the GIP, subject to satisfactory resolution of a number of open issues and l NRC comments. Action by SQUG and its contractors is underway to resolve the identified open issues and comments in accordance with the SQUG schedule presented at the August 10-11, 1988 meeting with the NRC staff and included the SQUG 1etter dated August 19, 1988. This schedule projects completion of Revision 2 of the GIP in Spring, 1989, contingent upon SQUG and NRC agreement on the resolution of the various open issues. Revision 2 of the GIP is the version which is scheduled to contain all of the information needed to implement the USI A-46 Feneric letter at SQUG member plants. The final NRC SER Supplement on Revision 2 of the GIP is anticipated by mid-1989.

During September, 1988, the work scope represented by Revision 0 of the GIP was presented to the Big Rock Point Technical Review Group (TRC) for their evaluation. Based on that evaluation the TRG has included this issue in the l Big Rock Point Integrated Plan as Item BN-14C, The TRG has indicated that implementation of this issue should be consistent with the schedule proposed 8810100261 800930 PDR ADOCK 05000155 P PNV g OC0988-0021S-NL01 l' t t \

Nuclear Regulatory Commission 2 Big Rock Point Plant Response to Generic SER September 30, 1988 L

by SQUG, with one specific exception. The exception is enclosed as l Attachment A to this letter. Upon completion of the final version of the GIP and after receipt of the supplemental SER associated with that revinion the issue will again be presented to the TRG for review and ranking. If there -

is a significant change in the work scope or the estimated cost of completing  ;

the SQUG program the TRG will reevaluate and rerank the entire issue.

Updates or changes to the plan and schedule for implementation of the SQUG commitments at the Big Rock Point Plant will be reported to the NRC as part of the semi-annual updates to the Integrated Plan for the Big Rock Point Plant.

  • ?

Y(L, '-\%.!~ (',c Kenneth V Berry  ;

Director, Nuclear Licensing CC Administrator. Region III, NRC NRC Resident Inspector - Big Rock Point ,

l i

i i

OC0988-0021S-NLO1

. . _ _ _ - - . , _ . . _ _ _ _ _ _ _ _ _ _ _ _ . . , _ _ _ _ _ __.._ _ _ _ . . _ . . ~ . _ - _ _ . - ._ _ _ _ _ ~ _ ,-

i *

+

i i

I l  !

t i

- i I

8 t

i ATTACHNENT A i j i j Consurr.ers Power Company

Big Rock Point Plant i j Docket 50-155 5

4 r

1 l

t 1

i SPFCIFIC EXCEPTION TO THE SQt'G CENERIC  ;

IMPLEMENTATION PROCEDURE. REV O ,

September 30, 1988 ,

] i f

i i

I

[

J i j

l I

i I

! e l I l

r J

i l  ;

.j l

d I

l i

j f 2 Pages OC0988-0021S-NL01 1

I 1

SPECIFIC EXCEPTION TO THE SQUG GENERIC IMPLEMEh"tATION PROCEDURE, REV 0 i, '

Q a Consumers Power Company has evaluated the commituents required by Revision 0 l of the GIP and has determined that the the following exceptions to the

requirements of the GIP are necessaryt I

I, GIP RFOUIREMENT  !

1  !

] 4.1.4 Anchorage Verification ,

l The licensee will verify anchorage adequacy with an approach incorporating  ;

i three eler.entet b '

1 1. Comparison of the anchorage adequsey with the seismic demand.

l

' Visual inspection of the anchorage to verify that it is properly 1

installed.

I i.

) 3. Visual inspection of the equipment anchorage connection to the j foundation to verify that there is adequate stiffness. *

)

) EXCEPTION / JUSTIFICATION

{

1. For areas within the Plant as described by the original Big Rock Point  !
Plant design with concrete coupressive strength of 3000 pai, the l

{ following criteria will be used to evaluate the equipment anchorages. l j l i a. For expansion anchor bolta with unknown manufacturers, the j allowables shall be in accordance with the guidelines used for the l i implementation of IE Bulletin 79-02 and IE Information Notice 4 1 80-21. l l  !

i b. For grouted in place anchor bolts, the allowables shall be

) evaluated using 3000 pai concrete compressive strength and the j methods delineated in the CIP.

j c. For expansion anchor bolts with a know manufacturer, the i allowables shall be in accordance with the manufacturer data using j the saec safety factor as delineated in the GIP and 3000 psi

! concrete compressive strength.

1

2. Prying action in base plates (or attachrents) using expansion anchors will be ignored as long as the base plates (or attachments) are within 1.6 times the allowable stresses for elastic design defined in Part 1 4

of the American Institute of Steel Construction Specification for the i

j OC0988-0021S-NL01 J

l

2 1

I Design, Fabrication, and Erection of Structura) Steel for Buildings, February 12, 1969. This is consistent with the evaluation criteria used by the Palisades Plant for the implementation of IE Bulletin 79-02 and IE Information Notice 80-21.

l 1

j 3. During the implementation of IE Information Notice 80-21 at the Big )

i Rock Point Plant, some expansion anchor bolts were recessed into i the floor and subsequently imbedded in grout. This makes the visual j inspection for tightness, gap determination, washer determination,

center to center dimension determination and edge distance determination impossible without removing the grout. Therefore, for

]

those anchor bolts that have been covered by grout, Consumers Power Company will rely upon plant drawings and other design and  ;

I construction documents to determine the location, spacing, torque l values, embedment depth, manufacturer and type of anchor bolt used, i

i i

r I

i

[

l J  !

i t

1 i l l

l 1

i oC0988-00215-N101 l

l,

!