ML19326D443

Responds to NRC Request During 750624 Meeting Re Reg Guide Implementation Review Program.Forwards Specific Reg Guide Subjs & Suggested Meeting Dates & Agenda

ML19326D443
Person / Time
Site:	Midland
Issue date:	07/03/1975
From:	Bauman R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Schwencer A US ATOMIC ENERGY COMMISSION (AEC)
References
1638, NUDOCS 8006110467
Download: ML19326D443 (10)

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j d.3/ 000hEU'l o.n... omc... m w.. u ena.n 4..no., s.cm.on, wcnm.n me, . 4,.. co . .i7 7 ..o..o July 3, 1975

, @, l h, h AlCEfy(f Mr. A. Schwencer, Chief Li 6ht Water Reactors Branch 2-3 C

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p. , g Division of Reactor Licensing 8  ;;ci gg $

US Nuclear Regulatory Commission Washington, DC 20555 p/ 'g0 MIDLAND PLANT El ~-

0 DOCKET NUMBERS 50-329, 50-330 REGULATORY GUIDE REVIEW MEETINGS FILE: 0505.2 SERIAL: 1638 During the June 2h, 1975 meeting between NRC and Consumers Pcwer Company mana6ement it was agreed that a program should be developed at this time for an in-depth review of Regulatory Guide implementation on the Midland Project.

In response to your request during the above referenced meeting, and con-firming recent communications with your staff, ve are attachin6 herewith a list of specific Regulatory Guides which should be discussed during a series of review meetings. It is anticipated that the following individual meetings vill be required:

General Subject Suggested Date W l ~

/f Electrical / Instrumentation July 1975 s' '

t, 3 sgjN T Civil / Structural / Con:truction August 1975

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Stress / Materials September 1975 f- Y , .5

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,/ Mechanical - Part I October 1975

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1 Mechanical - Part II November 1975 NI l l@ \sS Quality Assurance January 1976 The attached list covers Regulatory Guidec through 1.75 and indicates which ones may not be fully met by the Midland Plant design and therefore require discussion and resolution with the NRC. Draft positions on each of these guides were originally transmitted to the NEC vith the Consu=ers Power Company letter of June 28, 1974. Since that time some of the positions have required revision due 7i ?_. CJ 8006110 I[ 8

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to evolution of plant design and issuance of revised Regulatory Guides. In other cases the basic position relative to conformance has not changed, however the verbe.1 description has been revised. For these reasons a complete set of final positions vill be submitted to the NRC at least two weeks prior to each individual review meeting.

For the first series of meetings, it is recommended that discussions be limited to Regulatory Guides through 1.75 which was the original cutoff suggested in our letter of June 28, 1974. Since many of the Regulatory Guides beyond 1.75 have been recently issued, positions cannot be prepared in time to discuss them during the first series of meetings. It is suggested that discussions on Regulatory Guides beyond 1.75 be scheduled to follow the above specific review meetings.

During the June 24, 1975 discussion, it was agreed that the next meeting in this program should be at the Project Mana6ement level to establish specific ground rules, procedures, schedules, etc. We request that this meeting be scheduled for the week of July 14, 1975 and that the first technical meeting on Electrical /

Instrumentation be scheduled for the week of July 28, 1975 A proposed agenda for the Project Mansgement meeting is attached herewith. Representatives of the Consumers Power Ccapany, Bechtel and Babcock & Wilcox Project Management teams vill be in attendance.

Please advise if the above dates are acceptable. Comments on the proposed a6enda vill be appreciated.

JJ_w R. C. Bauman Project Engineer 4

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MIDIAND UNITS 1 and 2

• Review of Regulatory Guide Implementation Agenda For Meeting on Procedural Matters A. Background

1. Original vs Current Midland Plant Schedule

2. Need For Regulatory Guide Implementation Reviev

3. Consumers Power Company Basic Position on Implementation B. Review Procedures

1. Clarification of NRC " Draft Staff Position For Regulatory ,

Guide Conformance For The Midland Plant, Units 1 and 2"

2. Submittal of CPCo Positions - Schedule and Content a) Plent design and construction b) Quality Assurance c) Fuel

3. Procedure for Developing List of Items Considered by the l 1

Staff 'to be Absolutely Essential for Safety

4. Scope of Individual Technical Reviev Meetings

5. Schedule for Individua: Iechnical Review Meetings

. 6. Documentation of Review Results T. ' Special Procedures for Fuel Design and QA Reviev

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. -? . MEETING NO 1 .

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. ,7 Electri -i/Instirum'entation Group Agandb

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J Regulatory Guides - Electrical .

9 h ,p.1. R.G. 1.6 - Independence Between Redundant Standby (Onsite) Power i Sources and Between their Distribution Systems (3/10/71) l

.I g-2. 1.9 - Selection of Diesel Generator Set Capacity for Standby Power Supplies (3/10/71) p 3. 1.32 - Use of IEEE Std. 308-1971, " Criteria for Class IE Electric Systems for Nuclear Power Generating Stations" (8/11/72)  : .

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g-4. 1.41 - Preoperational Testing of Re'dundant Onsite Electric Power {

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Systems'to Verify Proper Load Group Assignments (3/16/73)

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5. 1.63 - Electric Penetration Assemblies in Containment' Structures for' Water - Cooled Nuclear Power Plants (10/73) ,

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. 6. 1.75 - Physical Independence of Electric Systems (2/74)

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Regulatory Guides'- Instrumentation

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6 1. R.G. 1.11 - Instrument Iines Penetrating P'rimary Reactor Containment (3/10/71) 2'. 1.12 - Instrumentation for Earthquakes (Rev. 1, 4/74)

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'g 3. 1.21 - Measuring and Reporting of Effluents from Nuclear Power Plants (12/29/71) ,

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1.22 - Periodic Testing of Protection System Actuation Function's

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5.- 1.23 - Onsite Meteorological Programs (2/17/72) 4

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6. 1.45 - Reactor Coolant Pressure' Boundary Leakage Detection Systems,

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(5/73) -

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7. 1.47 -' Bypassed and Inoperable Status Indication for Nuclear Power ,

- Plant, Safety Systems (5/73)

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8 .' l.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems (6/73) .

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t 9. .1.62'- Manual Initiation of Protective Actions (10/73)

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10. 1.73 - QuC ifice. tion Tests of Electric Valve Operators Installed *

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Incf.de .the Containment of Nuclear Powe'r Plants (1/7.4)

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g. . 2 aMidland Plant complies with this item, therefore minimum discussion required.

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.. . e. MEETING NO 2 Civil / Structural /C'onstruction Group Agcnda

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w Regulatrov Guides -

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1.10 - Mechanical (Cadweld) Splices in Reinforci.ng Bars of Er 1. R.G.

Category I Concrete Structures (Rev. 1, 1/2/73)

2. 1.15 - Testing of Reinforcing Bars for Category I Concrete Structures (Rev. 1, 12/28/72)

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3. 1.18 - Structural Acceptance Test for Concrete Primary Reactor Containments (Rev. 1,.12/28/72)

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4. 1.19 - Nondestructive Examinatian of Primary Containment Liner Ucids (Rev. 1, 8/11/72) ,

. 5. 1.27 - Ultimate Heat Sink (Fev. 1, 3/74) .

6. 1.35 - Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures (2/5/73)

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>;r 7. 1.55 - Concrete Placement in Category I Structures (6/73)

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8. 1.57 - Design Limits and Loading combinatio'ns for Metal ,

Primary Reactor Containment System Components (6/73)

}- 9. 3.59 - Dardgn Basis Floods f or Nuclear Power Plants (8/73)

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1.'60 - Design Response Spectra for Scismic Design of Nuclear Power Plants (Rev. 1, 12/73) .

11. 1.61 - Damping Values for Seismic Design of Nuclear Power

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..' P,lants (10/73) ,

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%!idland Plant complies with this item, therefore minimum discussion required.

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NEETING No 3

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Stress / Material's Group Agenda

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fu i

o Regulatory Guides

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41. R.G. 1.2 - Thermal Shock to Reactor Pressure Vessels (11/2/70)

2. 1.31 - Control of Stainless Steel Welding (Rev.1, 6/73) g

3. 1.34 - Control of Electroslag Weld Properties (12/28/72) g 4.

1.36-NonmetallicThermalInsulatignforhusteniticStainless Steel (2/23/73)

5. 1.43 - Control of Stainless Steci Weld Cladding of' Low-Alloy Steel Components (5/73)

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6. 1.44 - Control of the Use of Sensitized Stainless Steel (5/73)

7. 1.48 - Design Limits and Loading Combinations for Seismic Category I Fluid System Components (5/73)

8. 1.50 - Control of Preheat Temperature for Welding of Low-Alloy Steel (5/73) l i

9. 1.65 - Materials and Inspection for Reactor Vessel Closure

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Studs (10/73)

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10. l' 66 - Nondestructive Examination of Tubular Products (10/73)

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11. 1.71 - Welder Qualification for Areas of Limited Accessibility a' (1/,74).

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12. 1.72 - Spray Fond Plastic Piping (1/.74)

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' Midland Plant complies with this item, therefore minimum discussion required.

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NEETING NO 4 , e-)

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• M1chanical Group Agenda - Part I c

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Regulatory Guides

1. R.G. _1.1 - Net Positive Suetion'llcad for Emergency Cor'c Cooling and Containment Heat Removal System Pumps (11/2/70)

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, 4r 2. 1 13 - Fuel Storage Facility Design Basis' (3/10/71)

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1.14 - Reactor Coolant Pump Flywheel Integrity (10/27/71)

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.37 4.

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1.20 -- Vibration Measurements- on Reactor: Internals (12/29/71) - i

5. - - 1.26 - Quality Group Classifications and Standards (3/23'/72)'

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1.29 - Seismic Design Classification (Rev. 1, 8/73) -

7.. 1.40 - Qualification Tests of Continuous Duty Motors Installed

'Inside the. Containment of Water - Cooled Nuclear Power Plants (3/16/73) ,

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'S . 1.46 - Protection Against Pipe Whip Insi,de Containment (5/73)

?g 9. 1.49 - Power Levels of Nucicar Power Plants (Rev. 1, 12/73)

.k l0. 1.'51 - Inservice Inspection of ASME ' Code Class 2 and 3 Nuclear Pawar PJant Components (5/73) 7s . Installation of Overpressure Protection Devices (10/73)

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l.68 - Preoperational and In'itial Startup Test Programs for Water - Cooled Power Reactors (11/73)

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$- 13. _ l.70'- Standard Format and Con' tent of Saf ety Analysis Reports ' '

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. f6r' Nuclear Power Plants (Rev. 1, 10/72)

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" Midland Plant complies with this item, therefore minimum discussion required.

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/] M TING NO 5 .

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Mechanical Group Ahenda - Part II '

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• Regulatory Guides

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Af 1. R.G. 1.4 - Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressuri:cd

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Water Reactors (Rev. 2, 6/74)

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2. 1.7 - Control of Combustible Gas Concentrations in Containment Following a Loss of Coolant Accident (3/10/71) ,

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g ,3. 1.24 - Assumptionc Used for Evaluat,,ing the Potential Radiological Consequences of a Pressurized Water Reactor Gas

Storage Tank Failure (3/23/72)

'gP 4. 1.25 - Assumptions Used for Evaluating the Potential Radiological

- Consequences of a Fuci Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Rchetors (3/23/72) ,

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5. 1.42 - Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled *

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Nuclear Power Reactors (6/73)

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6. .1.52 - Design, Testing, and Maintenance Criteria for Atmosphere Cleanup Sys tem .'.ir Filtr,.t. inn .,nd Adsorption Units of Light-Water-Cooled Nucleat Powei Plar.ts (6/73)

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' Midland Plant complies with this item, therefore minimu:2 disuession required.

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A lEETING HO 6 *

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Quality Assurance / Operations Groun Ancada

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R3gulatory Guides _- Personnel Selection and Training (3/10/71)

) 1. R.G. 1.8 1.16 - Reporting of Operating Information (R'ev. 1, 10/73)

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1.17 - Protection of Nucicar Plants Against Industrial

• Sabotage (Rev. 1, 6/73)

(Design and

4. 1.28 - Quality Assurance Program Requirements Construction (6/7/72) 1.30 - Quality Assurance Requirements for the 'ustallation,

,5. Inspection, and Tescing of Instrumentation and Electric

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Equipment (8/11/72)

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1.33 - Quality Assurance Program Requirements (Operation)

(11/3/72) 1.37 - Qualit'y Assurance Requirements fo'r Cleaning of Fluid

7. Systems and Associated Components of Water-Cooled Nuclear Power Plants (3/16/73)

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1.38 - Quality Assurance Requircmcats for Packing, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants (3/16/73)

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1.39. - Hou: cheeping Requirements for Water-Cuvia ' !uclear Peua"

]) Plants (3/16/73) 10.

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1.54 - Quality Assurance Requirements for Protective Coatings Applied to Water-cooled Nuclear Power, Plants (6/73)

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1.58 - Qualification of Nuclear Power Plant Inspection, Examina-

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tion," and Testing Personnel (8/73) 12.

1.64 - Quality Assurance Program Requirements for the Design of Nuclear Power Plants (10/73)

13. 1,74 - Quality Assurance Terms and Definitions (2/74)

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l NRC DISTRIBUTION FOR PART SO DOCKET MATERIAL 1 2 (TEMPORARY FORM) i CONTROL NO: 7253 '

. FILE:

FROM: Consumers Power Company DATE OF DOC DATE REC'D LTR TWX RPT OTHER Jackson, Michigan R C Bauman

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7-3-75 7-8-75 XXX TO: ORIG CC OTHER SENTI:RC PDR Yv Mr Schwencer one signed SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXXXXXX ,,

1 , M 30 DESCRIPTION: ENCLOSURES:

Ltr re 6-24-75 meeting. . . .trans the foll- Schedule for implementation of reg guides owing: with regard to the licensing review for the Midland plant.....

% n rry:-- -- -

Mt.ru .i, m . - ~.LTm hm l.)

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PLANT NAME: Midland 1 & 2 _

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FOR ACTIDN/IMFORMATION 7-8-75 ehf BUTLER (L) REG AN (E)

W/ Copies JCH_V/ENCER WffCopies (L) ZIEMANN W/ Copies (L) W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L)

W/ Copies W/ Copies W/ Copies W/ Copies PAR R (L) VASSALLO (L) KNIGHTON (E) SPI:s W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOD (E) Lm g/1 c /.t ,-

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