ML20212J305

Discusses GL 97-06 Re Degradation of SG Internals,Dtd 971230.GL Requested Each PWR Licensee to Submit Info That Will Enable NRC Staff to Verify Whether PWR SG Internals Comply & Conform to Current Licensing Basis for Facilities

ML20212J305
Person / Time
Site:	Millstone
Issue date:	10/01/1999
From:	John Nakoski NRC (Affiliation Not Assigned)
To:	Necci R NORTHEAST NUCLEAR ENERGY CO.
References
GL-97-06, TAC-MA0925, NUDOCS 9910050101
Download: ML20212J305 (6)

Text

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M tx p . +1 UNITED STATES s'

-j NUCLEAR REGULATORY COMMISSION

• WASHINGTON, D.C. 20565-4001 49

• * * , * ,o October 1, 1999 Mr. R. P. Necci - Vice President Nuclear Oversight and Regulatory Affairs c/o Mr. David A. Smith Northeast Nuclear Energy Company .

P. O. Box 128

.Waterford, CT: 06385-0128

SUBJECT:

MILLSTONE NUCLEAR POWER STATION, UNIT NO,3 - COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 97-06, " DEGRADATION OF  ;

STEAM GENERATOR INTERNALS" DATED DECEMBER 30,1997 I l

(TAC NO. MA0925)

Dear Mr. Necci:

On December 30,1997, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter J

)

(GL) 97-06, " Degradation of Steam Generator Internals." This GL requested each pressurized-water reactor (PWR) licensee to submit information that will enable the NRC staff to verify whether PWR steam generator internals comply with and conform to the current licensing basis for their respective facilities, in GL 97-06, licensees were requested to submit information to the NRC within 90 days of the

- date of the generic letter, providing a written report that included the following for its facility-

. (1) Discussion of any program in place to detect degradation of steam generator internals and ,

a description of the inspection plans, including the inspection scope, frequency, methods, I and equipment.

The discussion should include the following information:

(a) Whether inspection records at the facility have been reviewed for indications of tube support plate signal anomalies from eddy current testing of the steam generator tubes that may be indicative of support plate damage or ligament cracking. If the addressee has performed such a review, include a discussion of the findings.

(b) Whether visual or video camera inspections on the secondary side of the steam generators have been performed at the facility to gain information on the condition of steam generator internals (e.g., support plates, tube bundle wrappers, or other components). If the addressee has performed such inspections, include a discussion 6 of the findings.

(c) Whether degradation of steam generator internals has been detected at the facility, ' Oh and how the degradation was assessed and dispositioned.

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9910050101 991001 PDR ADOCK 05000423 P PDR

1 October .- 1, i1999. .

! R. Necci (2) If the addressee currently has no program in p; ace to detect degradation of steam generator internale, include a discussion and justification of the plans and schedule for establishing such a program, or why no program is needed.

The NRC staff has completed its review of Northeast Nuclear Energy Company's March 30,

1998, response to GL 97-06," Degradation of Steam Generator Internals." The primary l purpose of GL 97-06 was to obtain information that would enable the staff to verify that the ,

l condition of pressurized water reactor steam generator internals comply with and conform to the current licensing bases for their respective facilities. The staff's review of your March 30, 1998, response to the GL did not identify any new concerns with the condition of the steam generator internals for the Millstone Nuclear Power Station, Unit No. 3 (MP3). The staff also did j not identify any concerns with the inspection practices employed to detect steam generator '

internals degradation. Thus, the staff concludes your response to the GL provides reasonable l

assurance that the condition of the steam generator internals for MP3 are in compliance with the current licensing bases. The detailed technical basis that supports this determination will be l published in a NUREG report. The staff expects to publish this NUREG in December 1999.

Your submittal provided both the information requested and the responses required by GL 97-06; therefore, TAC No. MA0925 is closed.

If you have questions regarding this action, please contact me at (301) 415-1278.

l Sincerely,

/S/

John A. Nakoski, Sr. Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page [)

DISTRIBUT ON 66 EAdensam (EGA1) Public JLinville, RI OGC SCoffin

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PD l-2 Rdg ESullivan ACRS JNakoski JClifford 50k DOCUMENT NAME: G:\PDI-1\ Millstone 3\ma0925close.wpd \

To receive a copy of this document, indicate in the box "C" copy w/o attar:h/enci "E" copy w/ attach /enct "N' no copy OFFICE PDI-2/PM . C PDI-2/LA .

E EMCB: input PDI-2/,SQ l NAME JNakoski M TClar8'//6) dated 9/16/99 JClifffd DATE 9 / 21/9Y 9 / 4 9 /99 [0 / / /99 OFFICIAL RECORD COPY i

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. s 3o October.1,;1999, i

I R. Necci (2) If the addressee currently has no program in place to detect degradation of steam generator internals, include a discussion and justification of the plans and schedule for establishing such a program, or why no program is needed.

~ The NRC staff has completed its review of Northeast Nuclear Energy Company's March 30, 1998, response to GL 97-06, Degradation of Steam Generator Internals." The primary i purpose of GL 97-06 was to obtain information that would enable the staff to verify that the l condition of pressurized water reactor steam generator internals comply with and conform to the current licensing bases for their respective facilities. The staff's review of your March 30, 1998, response to the GL did not identify any new concerns with the condition of the steam generator internals for the Millstone Nuclear Power Station, Unit No. 3 (MP3). The staff also did not identify any concerns with the inspection practices employed to detect steam generator internals degradation. Thus, the staff concludes your response to the GL provides reasonable l assurance that the condition of the steam generator internals for MP3 are in compliance with ,

the current licensing bases. The detailed technical basis that supports this determination will be l published in a NUREG report. The staff expects to publish this NUREG in December 1999.  ;

Your submittal provided 'both the intvrmation requested and the responses required by I

' GL 97-06; therefore, TAC 'No. MA0925 is closed. i If you have questions regarding this action, please contact me at (301) 415-1278.

Sincerely,

/S/

John A. Nakoski, Sr. Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 4 cc: See next page DISTRIBUTION Docket Files EAdensam (EGA1) Public JLinville, RI OGC SCoffin PD l-2 Rdg ESullivan ACRS JNakoski JClifford DOCUMENT NAME: G:\PDI-1\ Millstone 3\ma0925close.wpd To receive a con r of this document. Indicate in the box "C" copy w/o attach /enci"E" copy w/ attach /enci *N" no copy OFFICE PDl-2/PM . C PDI-2/LA . _ 6 EMCB: input PDl-2/,SQ NAME JNakoski @ TClarkMV dated 9/16/99 JCliffEd DATE 9 / 2 L/9M 9 / a19 /99 [0 / / /99 OFFICIAL RECORD COPY

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2 R. Necci i (2) If the addressee currently has no program in place to detect degradation of steam generator internals, include a discussion and justification of the plans and schedule for establishing such a program, or why no program is needed.

The NRC staff has completed its review of Northeast Nuclear Energy Company's March 30, 1998, response to GL 97-06, Degradation of Steam Generator Internals." The primary  !

purpose of GL 97-06 was to obtain information that would enable the staff to verify that the condition of pressurized water reactor steam generator internals comply with and conform to the current licensing bases for their respective facilities. The staff's review of your March 30, 1998, response to the GL did not identify any new concerns with the condition of the steam generator internals for the Mil! stone Nuclear Power Station, Unit No. 3 (MP3). The staff also dig i not identify any concerns with the inspection practices employed to detect steam generator

. internals degradation.' .Thus, the staff concludes your response to the GL provides reasonable

- assurance that the~ condition of the steam generator internals for MP3 are in compliance with l the current licensing bases. The detailed technical basis that supports this determination will be !

published in a NUREG report. The staff expects to publish this NUREG in December 1999. 1 Your submittal provided both the information requested and the responses required by GL 97-06; therefore, TAC No. MA0925 is closed.

if you have questions regarding this action, p!sase contact me at (301) 415-1278.

Sincerely, '

c= c Jo n A. Nakoski, Sr. Project Manager, Section 2 oject Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page -

y-4 k Ib Millstone Nuclear Power Station Unit 3 cc:

Ms. L. M. Cuoco Mr. F. C. Rothen Senior Nuclear Counsel Vice President - Nuclear Work Services Northeast Utilities Service Company Northeast Utilities Service Company P. O. Box 270 P. O. Box 128 Hartford, CT 06141-0270 Waterford, CT 06385 Edward L Wilds, Jr., Ph.D. Ernest C. Hadley, Esquire Director, Division of Radiation 1040 B Main Street Department of Environmental Protection P.O. Box 549 79 Elm Street West Wareham, MA 02576 Hartford, CT 06106-5127 i

Mr. James S. Robinson, Manager Regional Administrator, Region i Nuclear investments and Administration U.S. Nuclear Regulatory Commission New England Power Company  ;

475 Allendale Road 25 Research Drive j King of Prussia, PA 19406 Westborough, MA 01582 l

First Selectmen Mr. R. P. Necci l Town of Waterford - Vice President - Nuclear Oversight and l 15 Rope Ferry Road Regulatory Affairs Waterford, CT 06385 Northeast Nuclear Energy Company I P. O. Box 128 Mr. James Linville, Director Waterford, CT 06385 Millstone Inspections i Office of the Regional Administrator Deborah Katz, President 475 Allendale Road Citizens Awareness Network  !

King of Prussia, PA 19406-1415 P.O. Box 83  !

Shelburne Falls, MA 03170 Mr. M. H. Brothers .

Vice President - Operations Mr. Allan Johanson, Assistant Director i Northeast Nuclear Energy Company Office of Policy and Management '

P.O. Box 128 Policy Development and Planning Waterford, CT 06385 Division 450 Capito! Avenue - MS# 52ERN {

Mr. M. R. Scully, Executive Director P. O. Box 341441 l Connecticut Municipal Electric Hartford, CT 06134-1441 Energy Cooperative 30 Stott Avenue Ms. Terry Concannon Norwich, CT 06360 Co-Chair Nuclear Energy Advisory Council Mr. J. T. Carlin 415 Buckboard Lane Vice President - Human Services Marlborro, CT 06447 Northeast Utilities Service Company P. O. Box 128 Waterford, CT 06385

w s.

e Millstone Nuclear Power Station

. Unit 3 cc:

Mr. Evan W. Woollacott Citizens Regulatory Commission

. Co-Chair ATTN: Ms. Geri Winslow 3 Nuclear Energy Advisory Council P. O. Box 199 ' )

128 Terry's Plain Road Waterford, CT 06385 '

Simsbury, CT 06070 Mr. William D. Meinert Mr. John W. Beck, President Nuclear Engineer '

Little Harbor Consultt ats, Inc. Massachusetts Municipal Wholesale

~ Millstone -ITPOP Project Office Electric Company

- P.O. Box 0630 P.O. Box 426 Niantic, CT. 06357-0630 Ludlow, MA 01056 Mr. Leon J. Olivier Mr. B. D. Kenyon Senior Vice President and President and Chief Executive Officer-Chief Nuclear Officer - Millstone Nuclear Group Northeast Nuclear Energy Company Northeast Utilities Service Company P.O. Box 128 P.O. Box 128 Waterford, CT 06385 Waterford, CT 06385 Mr. C. J. Schwarz Mr. D. B. Amerine Station Director Vice President - Engineering Services Northeast Nuclear Energy Company Northeast Nuclear Energy Company l P.O. Box 128 P. O. Box 128 Waterford, CT 06385 Waterford, CT 06385

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Senior Resident inspector Mr. D. A. Smith l Millstone Nuclear Power Station Manager - Regulatory Affairs c/o U.S. Nuclear Regulatory Commission Northeast Nuclear Energy Company P. O. Box 513 P. O. Box 128 Niantic, CT 06357 Waterford, CT 06385 i i

Nicholas J.'Scobbo, Jr., Esquire Ms. Nancy Burton Ferriter, Scobbo, Caruso, & Rodo;:h:'c, P.C. 147 Cross Highway 75 State Street,7th Floor Redding Ridge, CT 00870

Boston, MA 02108-1807 ,

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