U-600630, Forwards Responses to NRC Questions Re FSAR Chapter 3 & 4 Amends.Necessary Changes Will Be Reflected in Future FSAR Amend.Issues Should Be Closed Out in Sser 6

Forwards Responses to NRC Questions Re FSAR Chapter 3 & 4 Amends.Necessary Changes Will Be Reflected in Future FSAR Amend.Issues Should Be Closed Out in Sser 6

ML20207B465
Person / Time
Site:	Clinton
Issue date:	07/16/1986
From:	Spangenberg F ILLINOIS POWER CO.
To:	Butler W Office of Nuclear Reactor Regulation
References
U-600630, NUDOCS 8607180049
Download: ML20207B465 (3)

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U-600630 g?

L30-86(07-16)-L 1A.120 ILLIN0/S POWER 00MPANY CUNTON POWER STATION, P.o. BOX 678, CLINToN, ILLINolS 61727 July 16, 1986 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Clinton Power Station FSAR Chapter 3 and 9

Dear Dr. Butler:

Illinois Power Company's responses to NRC Staff questions from the review of recent FSAR amendments are included in the attachment. In most cases the responses to the NRC Staff questions provide clarification for changes made to the FSAR. Responses requiring a change to the FSAR will be documented by this letter and the FSAR will be updated in a future amendment. It is expected that this letter will provide the basis for closing out these issues in Supplement No. 6 to the Safety Evaluation Report.

Please contact me if additional information is needed.

Sincerely yours, F. A. Spangenberg Manager - Licensing and Safety PJT/kaf Attachment cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Illincis Department of Nuclear Safety l

Regional Administrator, Region III, USNRC l

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m Attachmine to U-600630 Page 1 of 2 IP Response to NRC Staff Comments on FSAR Chapter 3 and 9 L The following NRC Staff comments have been resolved based upon the commitment to revise the FSAR.

1. Diesel Generator Starting Air System

, NRC Comment. FSAR Table 3.2-1, " Classification of Systems, Components and 1 Structures," page 3.2-19 item XXXVIII 7.b. The piping and valves on the Division 3 diesel generator starting air system should have Quality Assurance Requirements under 10CFR50, Appendix B during the operations phase.

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IP Response. FSAR Table 3.2-1 XXXVIII 7.b under the column, " Quality Assurance Requirements," will be changed from "N/A" to "B" to indicate that Appendix B requirements apply. Table 3.2-1 note (j) will be added under the " Comments" column which states:

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"(j) Those portions of piping and valves supplied by the diesel generator manufacturer meet the requirements of Safety Class 3, Quality Group C, Seismic Category I, although an "N" stamp will not be provided."

i Note (j) will be deleted from the " Comments" column for item XXXVIII 7.a.

2. Quality Groups S and T Classification NRC Comment. Quality Groups S and T need to be better defined. The terms are used on pages 3.2-28, 35 and 36. The footnote on page 2.3-36 is not-clear. Is Quality Group S identical to Quality Group B except that no authorized inspector involvement or N-stamp is required?

IP Response. Quality Group S nuclear safety-related instrumentation tubing l

1s designed, fabricated, installed, examined and tested in accordance with

the ASME Code Section III, Subsection NC requirements, except that no authorized inspector involvement or N-stamp is required.

Quality Group T nuclear safety related instrumentation tubing is designed, i fabricated, installed, examined and tested in accordance with the ASME Code Section III, Subsection ND requirements, except that no authorized inspector involvement or N-stamp is required.

FSAR Change. The Notes for Table 3.2-3, " Code Classification Groups -

Industry Codes and Standards for Mechanical Components," on page 3.2-37 will be revised to clarify the definitions for Quality Groups S and T.

Attechmint to U-600630 1

Page 2 of 2 The following NRC Staff comments were resolved without FSAR changes required.

1. Fuel Pool Heat Loads

, NRC Comment. FSAR Section 9.1.3.3.a (page 9.1-17), Is the heat load described in the FSAR section enveloped by the heat load described in the Safety Evaluation Report (SER) Section 9.1.3 (page 9-5). Is the require-ment in the Standard Review Plan (SRP) Section 9.1.3.1.d (page 9.1.3-6) of maintaining the pool below boiling reflected in the FSAR heat rate?

IP Response. The heat load in the FSAR is enveloped by the heat load described in the SER. The heat rate in the FSAR meets the SRP requirement of keeping the pool below boiling.

2. Standby Liquid Control System (SLCS)

I NRC Comment. FSAR Section 9.3.5.3 (page 9.3-15). The third paragraph states that the SLCS must be operable in the event of an offsite power failure and therefore the pumps, valves, and controls "are connectable" to the standby ac power supply. What does the word connectable mean?

IP Response. The word "connectable" is from the GE specification 22A3130 Rev. 5, sheet 7. The SLCS is not considered as part of the diesel 2

generator (DG) startup loads during a loss of offsite power because the SLCS pumps are normally deenergized. However, SLCS.is powered from Division I/II buses normally supplied by offsite power. In the event of a loss of offsite power or low voltage to the bus, the Division I/II diesel generators would start and supply power to the bus. The word "connectable" means that the SLCS pumps will be supplied by a normal or backup source of power, and not that the SLCS pumps "must be connected" to a power source to be made operable.

, 3. Refueling and Reactor Servicing NRC Comment. FSAR Section 9.1.4.2.10.2.4 (page 9.1-44). The maximum travel speeds for the trolley and the grapple hoist have been modified in i Amendment 35. Do these changes affect the heavy loads analysis?

IP Response. These changes reflect the actual design specification and do

, not affect the heavy loads analysis.

i l 4. Combustible Gas Control System NRC Comment. FSAR Section 9.4.5.5.1.2 (page 9.4-34). The CGCS equipment cubicle cooling system description does not address the auto start feature when temperature reaches 120*F as discussed on page 9-25 (last 3 lines) in the Safety Evaluation Report (SER). Has the 120*F room temperature feature been removed?

IP Response. The temperature limit switch at 120*F has been removed and the CGCS room coolers operate continuously.

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