ML19269D114

Responds to 781116 Ltr Detailing Category 2 & 3 Items for Consideration in Preparing Fsar.Will Address Items as They Are Implemented in Base Plant

ML19269D114
Person / Time
Site:	Marble Hill
Issue date:	02/21/1979
From:	Coughlin J PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To:	Boyd R Office of Nuclear Reactor Regulation
References
NUDOCS 7902270339
Download: ML19269D114 (4)

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7 L]5 PUBLIC SERVICE INDIANA February 21,1979 James Coughl n Vice Pret&nt -

Nuclear Mr. Roger S. Boyd, Director Docket Nos.: 50-546 Division of Project Management 50-547 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Const. Permit Nos.: CPPR 170 Washington, D.C. 20555 CPPR 171

Subject:

Marble Hill Nuclear Generating Station, Units 1 & 2 FSAR Content Regulatory Requirements Review Committee Category 2 and 3 items

Dear Mr. Boyd:

This is in response to your letter of November 16, 1978, detailing Category 2 and 3 items for our consideration in preparing the Marble Hill Final Safety Analysis Report.

The Marble Hill Nuclear Generating Station is a replicate project based on the Byron Station of Commonwealth Edison as noted in the letter from Mr. Ben C. Rusche to me dated November 3,1975. In accordance with the replication concept, and replication qualification issued to us in that letter, we utilized color photo copies of major portions of the base plant licensing document to identify those sections which were common to both plants and which the NRC Staff had reviewed and approved, and developed custom pages to fit those site unique topics which come under the Categories A through F in the letter, which need to be addressed for Marble Hill.

Marble Hill Station continues as a replicate project; it is our intent to follow the same procedure at the Operating License Stage, holding design changes to an absolute minimum from the base plant desig i other than required to fit the design to the Marble Hill site. We believe the continued use of the replication concept offers the maximum savings in review effort and additionally addresses the NRC's desire, also expressed in Mr. Rusche's letter, to carry on the replication concept through the completion of the OL review.

We have reviewed the list of NRC's Regulatory Requirements Review Committee (R3C) Category ? and 3 items attached to your November 16, 1978 letter for items which are unique to our project that come under the Categories A through F in Mr.

Rusche's letter. These items are identified on Attachment 1, following, and will be t

790227033i 1000 East Main Street, Plainfield, Indiana 46168 317. 839 .9611

Mr. Roger S. Boyd, Director February 21,1979 Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 adaressed as unique in the Marble Hill Final Safety Analysis Report. The other Category 2 and 3 items deal with areas of plant design which are common to both the base and replicate plants. Public Service Indiana will address these replicate items on Marble Hill as they are implemented on the base plant.

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ATTACHMENTI R C CATEGORY 2 MATTERS UNIQUE TO

-.- MARBLE HILL UNITS 1 & 2 Item Document Title / Unique Section

1. R.G.I.27, Rev. 2 Ultimate Heat Sink for Nuclear Power Plants / Unique paragraph is C.3 which refers to the retaining structures of the ultimate heat sink.

Remaining Regulatory Positions are replicate of the base plant.

2. R.G.I.91, Rev.1 Evaluation of Explosions Postulated to occur on Transportation Routes near Nuclear Power Plants /

This Regulatory Guide is unique in its entirety, and will be addressed in FSAR Appendix F.

3. R.G.I.137, Rev. O Fuel Oil Systems for Standby Diesel Generators (paragraph C.2) / Unique to Morbie Hill under para-graph C.2 are items 2.c, which requires periodic sampling of fuel oil per ASTM D975-74 and 2.d which requires procedures for removal of accumu-lated condensate in fuel oil storage tank.

4. R.G.8.8, Rev. 2 Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low As is Reasonably Achievable (Nuclear Power Reactors) / Unique sections are C.I.b(2),

C.I.c, C.2.d, and C.3.

5. BTP ASB 9.5-1, Rev.1 Guidelines for Fire Protection for Nuclear power plants / Compliance with portic ns of Appendix A are unique and will be addressed in the FSAR Appendix E, Fire Protection Report.

ATTACHMENT 1 (Continued)

R C CATEGORY 3 MATTERS UNIQUE TO MARBLE HILL UNITS 1 & 2 Item Document Title / Unique Section

1. R.G.I.101, Rev.1 Emergency Planning for Nuclear Power Plants / This Regulatory Guide is unique in its entirety and will be addressed in the FSAR Emergency Planning Volume.

2. R.G.I.ll4, Rev.1 Guidance on being Operator at the Controls of a Nuclear Power Plants / Unique Regulatory Guide sections are C.3, requiring administrative proce-dures to define and outline specific areas within the control room where the operator at the control should remain and C.4, requiring administrative procedures ensuring that the relief operator is properly briefed on plant status.

3. R.G.I.127, Rev.1 Inspection of Water Controlled Structure Associated with Nuclear Power Plants / Unique Regulatory Guide sections are C.3.a and C.4.b regarding hydraulic and hydrologic design and C.4.b subsequent inspection requirements.