ML19338C438

Discusses Issues & Positions to Be Resolved for Input Into Ser.Relief Request RI-02 Must Be Reviewed by Applicant. Preservice Program Must Be Amended.Addl Info Needed Re Max Operating Temp for Feedwater Control Rod Drive & Main Steam

ML19338C438
Person / Time
Site:	LaSalle
Issue date:	08/07/1980
From:	Thomas Taylor Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	Hum M Office of Nuclear Reactor Regulation
References
NUDOCS 8008150407
Download: ML19338C438 (3)

Text

.

" , ',s l%'

OBallelle Pacific Northwest Laboratories P.O. Box 999 Richland, Washington U.S.A. 99352 reiephone (509) 375-2338 Telex 15-2874 August 7, 1980 Martin Hum Materials Engineering Branch Division of Engineering Nuclear Regulatory Commission Washington, D.C. 20555

Dear Martin:

After reviewing my records on LaSalle County Unit 1, I find the following issues / positions need to be resolved for input into the SER.

1. The applicant must review the use of Relief Request RI-02.

This relief request relates to Class 2 bolting between one inch and two inches in diameter.

2. The preservice program must be amended to include NRC position on the use of IWC-1220(c), as outlined in the memo dated August 8,1979 from S. A. Varga to J.P. Knight.

3. The applicant needs to supply additional information for maximum operating temperature including design basis accident for:

• Feedwater

• Control Rod Drive

• Residual Heat Removal

• Reactor Core Isolation Cooling

• Main Steam

• High Pressure Core Spray

• Nuclear Boiler System

• Primary Containment Vent and Purge This information is needed to evaluate the applicant's Relief Request RI-03.

4 The applicant should provide additional information concerning design and construction (i.e. , do reinforcement saddles allow for decection of leakage) of main steam branch connections in Relief Request RI-07. XOO3 s

}O 8008150 407 6

a l4artin Hum August 7, 1980 2.

5. An NRC position on the use of Appendix III of the 1977 Edition of Section XI needs to be developed. This poisition will determine the acceptance / rejection of Relief Request RI-04,

6. The applicant will need to evaluate the impact of the memo from RSB concerning exemptions allowed by IWB-1220(b)(1).

Attachement i lists the systems, lines, sizes, etc. that the applicant currently exempts under IWB-1220(b)(1).

. If you have any further questions concerning LaSalle status, please 1

contact me. . _ _ _ _

Sincerely, T es~V s'\ -s.

T.T. TAYLOR Nondestructive Testing Section TTT:dd Attachment i

i i

1 l

l

ATTACHf1ENT 1 SYSTEM LINE SIZE LINE NUMBER PIPE THICKNESS

] MS 1.5" litSB8AA .281 l.5" 1MSB8AB .281 .

1.5" 1MSB8AC .281

1.5" '

1MSB8A0 .281

2.0" 1M505A .343

. 2.0" 1MS14AA .218 2.0" .

If1514AB .218 2.0" 1MS14AC .218 2.0" 1riS14AD .218 2.0" 1MS20AA .218 2.0" 1MS20AB .218 2.0" IfiS20AC .218 2.0" 1MS20AD .218 1.5" l!1520BA . P.18 1.5" lits 20BB .218 l.5" 1MS20BC .218 1.5" 1MS20B0 .218 Nuclear Reactor 2.0" if1Bb5A .343 2.0" 1NB07A .343 2.0" ThB08A .343 2.0" 1NB09A .343-2 . 0 111B011 A .343 2.0" 1NB0138 .343 2.0" 1NB16A .343 2.0" 1NB19A .343 2.0" lNB20A .343 2.0" 1NB21A .343 -

2.0" If1322A .343 2.0" 1NB24A .343 RHR 2.0" 1RHB4AA .344 2.0" 1RHB4AB .344 RCIC 2.0" 1RIO9A .344

! 2.0" 1RIO9B .218 Reactor Recirc. 2.0" 1RR28A .344 Stand-by Liquid 1.5" ISC028 .

Control 1.5" 1SC02BA l 1.5" ISC02BB

- ,, ,. -- - - , - . - - - - - - - - - , . , . - . -. ,-- --