ML20087E211

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Submits Addl Info on Generic Ltr 82-33 Schedule Requirements for Emergency Response Capabilities.Vendor of New Computer Sys Requested 1-yr Delay to June 1985 for Delivery,Affecting Schedular Commitments Made to NRC
ML20087E211
Person / Time
Site: Point Beach  
Issue date: 03/08/1984
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8403160080
Download: ML20087E211 (4)


Text

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-l MSC0nSin Electnc ma couraur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEZ, WI 53201 March 8, 1984 Mr. H. R.

Denton, Director Office of Nuclear Reactor Regulation U.S. NUCLEAR REGULATORY COMMISSION Washington, D.C.

20555 Attention:

Mr.

J. R. Miller, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 ADDITIONAL INFORMATION ON GENERIC LETTER 82-33 i

SCHEDULE REQUIREMENTS FOR EMERGENCY RESPONSE CAPABILITIES l

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In letters dated April 15 and August 24, 1983 Wisconsin Electric provided a description and schedule for implementation j

of our emergency response activities.

Those submittals were in response to Mr. D. G. Eisenhut's letter dated December 17, 1982, Generic Letter 82-33 entitled " Supplement 1 to NUREG-0737 - Re-quirements for Emergency Response Capability".

The August 24 letter updated the schedular commitments we made in the April 15 letter.

We have recently received a request by the vendor of our new plant computer system for an additional one year delay in delivery from June 1984 to June 1985, due primarily to vendor problems in developing the computer system software.

The delay affects a number of schedular commitments we have made in the past.

This letter details the resultant schedule modifications.

l The number and letter designation for each item matches those contained in our August 24, 1983 letter.

4.

Safety Parameter Display System (SPDS)

As described in our previous submittals, the Safety Assessment System (SAS) is our version of the SPDS and is part of the new computer.

Therefore, the SAS in-stallation and operation will similarly be delayed by about one year.

We still anticipate that by about six months after delivery, the computer and the SAS can be installed and operational.

We therefore anticipate the SAS to be operational on or before December.31,-

1985.

Also, the description ~and safety analysis

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Mr. H.

R.

Denton March 8, 1984 submittal scheduled for April 30, 1984 will be delayed until April 30, 1985.

In the August 24, 1983 letter we had noted that certain instruments which are part or the new computer and the SAS, principally tne final configuration of the core exit thermocouples, would not be operational until the next outages after computer startup.

Even with the additional delay in the computer system delivery, we have continued to proceed with the modification work in containment and with interim installations outside containment such that these instruments can be con-nected to the computer during computer installation and will not require an additional outagc for final connec-tion.

They will, therefore, become operational in their final configuration at the same time as the computer system.

5.

Detailed Control Room Design Review Although the SAS will not be operational, we still plan on performing the Control Room Design Review as previously scheduled.

6.

Regulatory Guide 1.97eApplication to Emergency Response Facilities We submitted our report describing how we meet the req lrements of Type A, D, C, D and E variables as described in Regulatory Guide 1.97 in a letter to the NRC dated September 1, 1983.

We are waiting for NRC evaluation of this report.

Note that the delay in the computer delivery will delay the completion of tha final display configuration of some Regulatory Guide 1.97 instruments until December 1985.

However, those affected instruments are or will be in an interim display configuration, in accordance with the schedule in our September 1, 1983 submittal.

7.

Upgraded Emergency Operating Procedures (EOP's)

We will be providing further information on the schedule for the new EOP's in a separate letter in the near future.

8.

Emergency Response Facilities 8 A.1 Technical Support Center (TSC)

We still plan on completing the emergency power supply to the TSC by December 1984 based on equipment delivery before November 1984.

As discussed previously in this letter, oper-ability of the SAS has been delayed until-December 1985.

Since the final TSC instru-

~

Mr. H. R. Denton March 8, 1994 mentation displays are an integral part of the computer output display system, final oper-ability of the TSC instrumentation is dependent upon the computer and will not be complete until that date.

The current plant parameters displayed in the TSC, as described in Table 2.2.2.b-2 of our March 14, 1980 submittal, will continue to be provided using interim loop configurations.

(The parameter noted as Pressurizer Wide Range Pressure - Unit 1 and Unit 2 is actually direct Reactor Coolant System Wide Range Pressure - Unit 1 and Unit 2.)

A complete description of the plant data collection, storage, analysis and display system will be provided as part of the descrip-tion and safety analysis discussed in Section 4 of this letter.

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

Buildings Since receiving denial from the NRC for our exemption request to locate the Point Beach EOF in our corporate' headquarters, we have located the Emergency Support Center in the newly completed Site Boundary Control

-Center building.

Our letter of November 18, 1983 provides a description of the EOF.

b.

Instrumentation EOF instrumentation is dependent on the computer installation schedule discussed earlier.

8.D Meteorology and Dose Assessment

1. Hardware The primary and backup towers are complete.

There is no change in the' schedule for the Lake Brcoze Effects Tower au discussed in the August 24, 1983 letter.

.:2. Software Software development of the. meteorology and dose assessment program is essentially complete, except for integration and checkout ~on the new computer.

These latter activities cannot be

-completed until after delivery of.the new com-puter as discussed. earlier.

Much'of.the required. cabling 11s in place,~except for.a.few q

m

Mr. H. R. Denton March 8, 1984 short runs and the computer terminations themselves which are dependent on installation of the new computer.

3. Submittal As stated in the August 24 letter, we still expect to provide a complete description of the meteorological and dose assessment hardware and software by October 1, 1984.

Other items not specifically addressed in the April 15 and August 24 letters, which will not be in their final config-uration until the computer is completed, include the subcooling monitors and the Reactor Vessel Water Level System.

Currently one of two subcooling monitor channels from each unit is connect-ed to a subcooling display temporarily located in an auxiliary rack in the computer room.

The second channel from each unit is connected to the backup computer with continuous CRT display in the control room.

These subcooling displays are based on wide range RCS pressures and wide range hot leg loop (RTD) tempera-tures.

The final configuration will include the capability to display subcooling based on thermocouple temperatures as well.

Currently a subcooling indication based on the thermocouples is available through the existing plant process computers.

One uncompensated reactor vessel water level channel from each unit is connected to the backup computer with continuous CRT display in the control room.

Compensated level will be available when the new computer becomes operational.

As stated earlier in this letter, we have received a formal request from our computer system vendor to revise the con-tract schedule for delivery of the system from June 1984 to June 1985.

We have not yet indicated our concurrence with the ven-dor's requested schedule revision, pending resolution of other related ccntractual matters and the provision of reasonable assurance that a new schedule will be met.

We will keep you advised of any schedular developments, and we will continue to do all we can to complete this project in an acceptable manner and on a timely basis.

Should you wish to discuss these matters further, please contact us.

Very truly yours, Vice_ President-Nuclear Power C. W. Fay Copy to NBC Resident Inspector