ML20054J485

Requests Addl Info Re Auxiliary Feedwater Header Repair Reported in RO 287/82-06 on 820514

ML20054J485
Person / Time
Site:	Oconee
Issue date:	06/23/1982
From:	Novak T Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NRR-821920, NUDOCS 8206290090
Download: ML20054J485 (4)

Text

_ _ _ _

~g * '

s>

M~ M~ *)]s F qs g we

, .r JUNE 2 3 I!E DISTRIBUTION Cuocket Fil@ TNovak NRC PDR WJohnston Docket No. 50-287 L PDR Program Support Branch NRR-821920 ORB #4 Rdg

!!r. William O. Parker, Jr. AE0D D b6O/h Vice President - Steam Production IE Duke Power Company ACRS -10 P. O. Box 33189 PWagner 422 South Church Street RIngram Charlotte, North Carolina 28242 Gray File EBlackwood

Dear fir. Parker:

H0rnstein JKnight SUDJECT: AUXILIARY FEEDWATER HEADER REPAIR - REQUEST FOR ADDITIONAL INFORMATION Following the reported discovery of damage at the Davis-Besse facility, Duke Power Company perfomed inspections of the once-through steam generator internal auxiliary feedwater headers at the Oconee 3 facility. The results of the inspections and preliminary plans for repair have been reported in your Reportable Occurrence Report R0-287/82-06 dated May 14, 1982.

We have reviewed the available infomation regarding your planned repairs and find that additional information is required for our reviews. Therefore, pursuant to 10 CFR 50.54(f), we request that you provide us your responses to the following items, no later than 10 days prior to scheduled restart.

Your responses must be submitted to the NRC, signed under oath or affirmation, to enable the Commission to determine whether or not your license shall be n'odified, suspended, or revoked.

1. Provide a detailed description of the repairs and nodifications to the auxiliary feedwater system. Describe how the as modified system compares to the auxiliary feedwater design used previously in other operating B&W plants. Compare the expected perfomance of the modified design to that of the original design and of earlier B&W units.

2. Describe the program to identify and recover loose parts resulting from previous damage and those that may be produced during repair. Describe your loose parts nonitoring system (s) and discuss detection capability partic-ularly with reference to any known or potential loose parts. If loose parts will exist after operation, evaluate the safety consequences.

8206290090 B20623 PDR ADOCK 05000287 4' P PDR BAYEf suc ev=u u no somacu om OFFICIAL RECORD COPY ** "-"*

~

~ y . ~ n .s n w, J . .

~

s y

!!r. William O. Parker 3. Describe the types of pre-repair inspections performed on the steam generator shell, shroud and header and discuss the results. Supply a drawing or drawings which show the limits of each inspection performed.

Identify the criteria used to evaluate the soundness of the header and discuss, where applicable, the ability of the remote visual inspections to detect flaws with respect to the acceptance criteria.

4. Describe the original criteria for minimum acceptable clearances between the AFW header and supports and the peripheral tubes, and relate this to the clearances that will exist after repairs are completed. If clearances after repair are less than the minimun acceptable for the original design, provide the necessary analyses to justify operation under normal, transient, and accident conditions.

5. Discuss your criteria and procedures for plugging.and stabilizing of peripheral tubes.

6. Provide an analysis which demonstrates acceptable results when naximum expected forces are applied to the stabilized header considering normal, transient, and accident conditions.

7. Describe your acgeptance criteria for all welds used to stabilize or reinforce the header. Describe in detail the inspection program to be followed.

8. What inspections will be performed following the stabilization of the header to ensure that distortion from welding does not reduce clearances between tubes and the header below the mininun acceptable?

9. Provide an analysis of AFU flow induced tube vibration for the nodified AFW design.

10. Describe your plans for revision of the ISI/IST program to include steam generator internals on the stean side.

11. Describe the post-repair startup test and inspection program, including water hammer tests, to be conducted prior to the resumption of power operations.

Since your proposed repairs include changes in the facility, which involve an un-reviewed safety question, !!RC approval will be required prior to facility operation.

The reporting requirements contained in this letter affect fewer than ten respondents; therefore, OMD clearance is not required under P.L.96-511.

Sincerely,

=,. : . : . -:.. ~~a . , .r .

Thomas !!. Novak, Assistant Director

• See_pr1Ylaus_Wilite for conc. , for Operating Reactors 6#2-/82 i

.. 0RBM: Dh .hb.$h.3.:N ,N;Qit;ik. AD:CSE:DE AD:MEB :DE

. Mn'ldhtW 'WJ6h6ft'6rir

""" PWagner;cf JStolz* M

.cci..Sce.next.pAge.

, 6/15/ 82., 6 82 6/,15/82 6/,15/82

.l.6M R2 we.ow m a ~ %c" W a OFFICIAL RECORD COPY " " ~ ~

( - .

r

• .$:t ,

k e f

N Mr. William O. Parker 3. Present, in detail, the types of pre-repair inspections perfomed on the steam generator shell, shroud and header and discuss the results. Supply a drawing or drawings which show the limits of each inspection perfomed.

Identify the criteria used to evaluate the soundness of the header and discuss, where applicable, the ability of the remote visual inspections to detect flaws with respect to the acceptance criteria.

4. Provide the original miniaun acceptable clearances between the AFW header and supports and the peripheral tubes and relate this to the clearances that will exist after repairs are completed. If clearances after repair are less than the minimum acceptable for the original design, provide the necessary analyses to justify operation under nomal, transient, and accident conditions.

5. Discuss your plans for plugging and stabilizing of peripheral tubes including details of how ?ny tube stabilization will be accomplished.

6. Provide an analysis of the maximum forces on the stabilized header considering nomal, transient, and accident conditions.

7. Describe your acceptance criteria for all welds used to stabill:e or reinforce the header. Describe in detail the inspection program to be followed.

8. Vhat inspections will be perfomed following the stabilization of the header to ensure that clearances between tubes and the header have not been reduced below the mininum acceptable due additional distortation fron welding.

9. Provide an analysis of AFW flow induced tube vibration for the codified AFU design.

10. Describe your plans for revision of the ISI/IST program to include stean generator internals on the steam side.

11. Describe your plans for conducting water hammer tests on the nodified AP.!

systen.

The reporting requirenents contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-611.

Sincerely,

v. . . . . . w gg Darrell G. Eisenhut, Director Division of Licensing cc: g next page Y J f' "#""

"[

omcr > ........QRM.kk. #4: A: R:DL, ,hh,CSE:DE ,,A Q g D DL,. ,g, ,~d f,,, ,

s Il, DL , , , ,

y li PWagner;cf sunuur> .................... JSt ,..n. . . . . . . . . .. JKn Ufit. .b,..A.

.. . . .... ..J.oi

. on s .,,. .. .n.

dei s e..nh u.t.. 6..~*..".........

om>

6

. //M.82 . , , , , ,

s/,

......(L/

82 2,g /8 ,

s/g/82,J ,

szig82 6/..../82_ . e s 2- ..

t sac ronu ats pam.ncu o2e OFFICIAL RECORD COPY usapo. mi_um

i, .

'. Duke Power Company It cc w/ enclosure (s):

,, Mr. William L. Porter

!' Duke Power Company P. O. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Oconee County Library 501 West Southbroad Street Walhalla, South Carolina 29691

. Honorable James M. Phinney I County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator Ii U. S. Nuclear Regulatory Commission, Region II 1 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.E.

Atlanta, Georgia 30308 William T. Orders Senic Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 ,

Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue -

Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.

DeBevoise & Liberman 120017th Street, N.W.

Washington, D. C. 20036

.