ML20080D620

Suppls 830415 Response to Generic Ltr 82-33 Re Schedule Requirements for Emergency Response Capabilities,Per Suppl 1 to NUREG-0737.Implementation Dates for Emergency Response Capabilities Revised as Listed

ML20080D620
Person / Time
Site:	Point Beach
Issue date:	08/24/1983
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM GL-82-33, TAC-53345, TAC-53346, NUDOCS 8308300521
Download: ML20080D620 (5)

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h lMsconsin Electnc mea couraur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 August 24, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention

Mr. R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 SUPPLEMENTAL RESPONSE TO GENERIC LETTER 82-33 SCHEDULE REQUIREMENTS FOR EMERGENCY RESPONSE CAPABILITIES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In a letter dated April 15, 1903 we provided a description of our plans and schedule for a phased implementation and integration of our emergency response activities. This information was in response to Mr. D. G. Eisenhut's letter dated December 17, 1982, Generic Letter No. 82-33, " Supplement 1 to NUREG-0737 Requirements for Emergency Response Capability". As discussed in the April 15 letter, the commitment dates we provided assumed a best effort implementation and that interim steps discussed in the attachment to the letter could be reached on schedule. Subsequent to the April 15 date, we have experienced or are aware of several delays in these interim steps and have, therefore, revised a number of the implementation dates for these emergency response capabilities.

This letter details these schedule delays. The number and letter designation for each item matches those found in the attachment to our April 15 letter.

4. Safety Parameter Display System (SPDS)

We have been advised by the vendor that the delivery date for the new computer system will be delayed until l June 1984. We had anticipated that by about six months I after delivery the computer could be installed and operational.

In addition, we had noted that certain instruments that are part of the computer and safety assessment system (SAS),

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l principally the. core exit thermocouples, would not be operational until the next unit outage. Accordingly, to ,

accommodate-this shipping delay, the computer installation,  !

and the completion of the outage dependent instrumentation we have rescheduled the SAS to be operational on'or before December 31, 1984. .In a similar manner, the description l

' and safety analysis submittal scheduled for September 30, j 1983 will be delayed until April 30, 1984.

5. Detailed Control Room Design Re/iew Although the schedule for completion of the SPDS, imple-montation of emergency operating procedures, and Regulatory l

Guide 1.97 instrumentation has been delayed as discussed

elsewhere in this letter, we presently anticipate no j delays in the schedule for the' control-room design-_ review.

! discussed in our April 15 letter.

1 6. Regulatory Guide 1.97 - Application to Emergency Response

! Facilities No change to the submittal date as discussed in our i April 15 letter.

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7. Upgraded Emergency Operating Procedures (EOP's)

Revision 1 of the Emergency Response Guidelines has not yet been issued by the Westinghouse Owners Group.

Although the revision should be issued later this month, additional background materials from the owners Group needed to revise the EOP's will not be available until December 1983. The emergency operating procedures 1 writing effort will therefore.not-be completed until February 1984. Verification and validation will then i

be completed approximately mid-June with final approved l procedures issued by mid-July 1984. It is anticipated j that operator training can be completed by: October 1984

and-implementation of the upgraded EOP's in the control-1 room can be achieved coincident with'the new instrumenta-4 tion and systems.in December 1984..

I Our April 15 letter committed to_ submittal ~of a procedures

' generation package to the NRC by-December 11, 1983. .This submittal willfof necessity.be delayed to April 1984.

8. Emergency Response Facilities t

8.A.l. ' Technical' Support Center '(TSC) i l-Due to. delays in the design and delivery of the required _ emergency power switchgear, emergency power'to the TSC as described.in our April 15 letter will now-be completed by. December 1984.

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e i Mr. H. R, Denton August 24, 1983 We have been advised by your staff that full operation and functionality of the TSC is dependent upon providing Regulatory Guide 1.97 instrumenta-tion to the TSC. As discussed previously in this letter, operabilits- of the SAS has been delayed until December 1984. Accordingly, in keeping with your criteria for operability of the TSC, this facility cannot be considered complete until that date.

8.A.3. Emergency Operations Facility (EOF)

a. Buildings The new Site Boundary Control Center building has experienced minor construction delays due to late delivery of HVAC components.

Occupancy originally scheduled for September 1, 1983 has been rescheduled to October 1, 1983.

The' communications equipment installation schedule remains unchanged and is expected to be complete by December 31, 1983. We have not yet received a written response from NRC regarding our exemption request to locate a portion of EOF functions in an Emergency Support Center (ESC) at our. corporate head-quarters. Accordingly, the disposition of our EOF remains unresolved,

b. Instrumentation EOF instrumentation is dependent on resolution of the ESC location and is tied to the computer installation schedule as discussed earlier.

8.C. Staffing As you are aware, the Commission has concluded in its safety evaluation attached to Mr. J. A. Hind's letter to licensee dated June 10, 1983 that the program for on-shift staffing and augmentation for emergency situations at the Point Beach' Nuclear Plant meets the requirements of 10 CFR Part 50.47 Appendix E and Supplement 1 of NUREG-0737 and is acceptable. We therefore consider that, subject to your past implementation inspection and verifi-cation, no further action is necessary on this topic.

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Mr. H. R. Denton August 24, 1983 8.D. Meteorology and Dose Assessment

1. Hardware

a. Primary Tower Equipment on this tower is fully functional at both 10 and 45 meter levels except for the heaters on the anemometer and the wind direction sensor. Recorders for this instrumentation, which are located in the control room, are also fully functional.

The old power and telemetry cable is still being used and remains to be replaced. The permanent power supply must also be added.

b. Backup Tower Equipment on this tower, as well as the control room recorders, is installed and fully functional.

c. Lake-Breeze Effects Tower The equipment for this tower has been procured; however, the final location has not yet been determined. The location will be chosen by June 1984 with installation completed by October 1984.

2. Software The software vendor is on schedule. However, completion is tied to installation of the new computer as discussed earlier.

3. Submittal Because of the delay in the computer shipping I schedule, we expect a similar delay in providing a complete description of the meteorological  ;

and dose assessment hardware and software to l October 1, 1984.

4 Mr . II . R . Denton August 24, 1983 Should you have any questions concerning the information provided in this letter or require additional details regarding these delays, please let us know. We shall continue to do all we can to satisfactorily complete these schedular commitments.

Very truly yours, M' r /

Vice Presiddnt-NI1 clear Power C. W. Fay Copy to NRC Resident Inspector Subscribed and sworn to before me this A d day of August 1983.

M: Y WW !.:_ -

Notdrf ?upc, Stat 5 of Wisconsin My Commission expires L_ A /., .Jg 2 y. - ,

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