ML20028F640
| ML20028F640 | |
| Person / Time | |
|---|---|
| Site: | North Anna, Crystal River, Ginna, 05000000 |
| Issue date: | 12/13/1982 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Schlissel D NEW YORK, STATE OF |
| Shared Package | |
| ML20028F641 | List: |
| References | |
| FOIA-82-534 NUDOCS 8302020343 | |
| Download: ML20028F640 (5) | |
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NUCLEAR REGULATORY COMMISSION 4
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Docket No. 50-244 fp-l6Y, gy JU!
Mr. David A. Schlissel State Consumer Protection Board 99 Washington Avenue IN RESPONSE REFER Albany, NY 12210 TO F01A-82-534
Dear Mr. Schlissel:
This is in further response to your letter dated November 1,1982, in which you requested, pursuant to the Freedom of Information Act, access to records for inspection and copying concerning seven subject categories as specified in your letter.
l In further response to your request we have identified the additional documents listed on Appendix A.
Copies of these documents are being placed in the NRC Public Document Room (NRC PDR), located at 1717 H Street, N.W., Washington, DC 20555, where they will be available for public inspection ar.d copying, and copies of these documents are enclosed for your use.
I Also, we offer the following additional comments on item 3 of the seven items listed in your letter.
Item 3:
Concerning the February 1980 discovery of loose parts in a steam generator at the North Anna 1 facility -
See Appendix A documents 21, 22, and 23.
Concerning the March 1978 discovery of loose parts at the Crystal River 3 facility - See Appendix A i
documents 24 through 27.
We note from the referen:es in your request letter, that you are apparently already in possession of a copy of the NRC document NUREG-0916, " Safety Evaluation Report Related to Restart of R. E. Ginna Nuclear Power Plant (252 pages).
8302020343 821213 PDR FOIA SCH.ISS82-534 PDR
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Mr. David A. Schlissel I As explained by Mr. Frank W. Karas of my staff in his telephone conversations with you on November 29 and 30,1982, the NRC's Mr. Emmitt C. Murphy
,I (301) 492-8434 will be in telephone contact with you-to answer any l
questions you may have concerning the subjects of your request not covered by the documents already in the NRC PDR or those being made 1
available in response to your request.
Our search for documents which may be subject to your request is continuing, and we will communicate with you again' when our search efforts are completed.
Sincerely'f'
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. Felton, Director Division of Rules and Records i
Office of Administration i
Enclosures:
As stated J
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iblA 32-534 0
0 Apppndix A i
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10/26/73 WASH-1284, Guidance On Quality Assurance Requirements During The Operations Phase Of Nuclear Power Plants, US AEC (142 pages) 2.
5/24/74 WASH-1283, Revision 1, Guidance On Quality Assurance Requirements During Design and Procurement Phase of Nuclear Power Plants -
Revision 1, US AEC (181 pages) 3.
11/16/79 IE Information Notice No. 79-27, Steam Generator Tube Ruptures At Two PWR Plants, NRC Accession No. 7910250488 (11 pages) 4.
4/5/82 Task Interface. Agreement, Task No. 82-05 (1 page) w/ attachment:
5/19/82
!!emorandum for D. G. Eisenhut, from R. W. Starostecki,
Subject:
GINNA SER INPUT - TASK NO. 82-05 (4 pages) 5.
10/15/76 Licensee Event Report No. LER-280/76-12B, VEPC0, Docket No.
50-280, Surry Unit 1,, license No. DPR-32 (5 pages) 6.
' 11/17/76 Licensee Event Report No. LER-280/76-138, VEPCO, Docket No.
50-280, Surry Unit 1, license No. DPR-32 (5 pages) 7.
10/8/76 Reportable Occurrence Report No. R0-280/76-07B, VEPC0, Docket No. 50-280, Surry Unit 1, license No. DPR-32 (5 pages) 8.
10/15/76 Licensee Event Report No. LER-281/76-058, VEPCO, Docket No, i
50-281, Surry Unit 2,. License No. DPR-37 (5 pages) 9.
1/5/76 Letter to LPOR re: documents sent which relate to Florida Power & Light Company, Docket Nos. 50-250 and 50-251 (Turkey Point Units 3 and 4) (4 pages) j 10 12./9/75 Letter to R. E. Uhrig (FPL) frorn N. C. floseley (NRC) w/ Inspection Report Nos. 50-250/75-16 and 50-251/75-16 (19 pages) 11.
2/13/76 Letter to LPDR re: documents sent which relate to Florida
- Power & 'aght Company, Docket Nos. 50-250 and 50-251 (Turkey 1
Point Units 3 and 4) (7 pages) 12.
1/13/76 letter to R. E. Uhrig (FPL) from F. J. Long (NRC) w/ Inspection j
Report Nos. 50-250/75-17 and 50-251/75-17 (20 pages) 13.
8/1//5 l etter to R. E. Uhrig (FPL) from N. C.1toseley (NRC) (1 page) w/ enclosure: 7/14/75 let ter to N. C. l'oscley (NRC) from i
R. E. Uhrig (TPL) (2 pages) 14.
6/25/75 l etter to R. E. Uhrig (FPL) frun N. C. lioseley (HRC) (2 pages) u/ encl osu re: IE Inspection Report Nos. 50-250/75-8 and 50-251/75-8 (14 pages) 15.
//21//5 letter to R. E. Uhrig (I PL) fro n N. C. I'.oseley ( ;RC) w/ enclosures:
7/21/75 letter to LPOR f rom N. C. l'eseley (NRC) (1 pace); 6/20/75 letter to N. C. Itoseley (NRC) frcca R. E. Uhrig (fPL) (I pace)
Re-fv!A,2 $34 O
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_ Appendix A 16 5/29/75 Letter to R. E. Uhrig (FPL) from N. C. Moseley (NRC) (2 pages) w/ enclosure: IE Inspection Report Nos. 50-250/75-7 and 50-2Sl/75-7 (10 pages) 17.
1/21/76 Letter to LPDR re: documents sent which relate to Carolina Power and Light Company, Docket No. 50-261 (H. 5. Robinson, Unit 2) w/ enclosures - As stated 18.
1/13/76 Letter to LPDR re: documents sent which relate to Carolina Power & Light Company, Docket No. 50-261 (H. B. Robinson, Unit 2) w/ enclosures - As stated (25 pages) 19.
1/14/77 Letter to W. L. Proffitt (VEPCO) from F. J. Long (NRC)
(5 pages) 20.
10/21/76 Letter to W. L. Proffitt (VEPCO) from F. J. Long (NRC) w/e'nclosu re: IE Inspection Report Nos. 50-280/76-14 and 50-281/76-14 (15 pages)
Re:
F01A-82-534 Appendix A (Continued)
- 21. 2/4/80 Letter to W. L. Proffitt (VEPCO) from A. Schwencer (NRC),
Subject:
Safety Evaluation Report for the Steam Generator Inspection and Maintenance at the North Anna Power Station, Unit No. 1, NRC Accession No. 8003280020 (4 pages) 22, 2/26/80 Letter to J. H. Ferguson (VEPCO) from J. P. O'Reilly (NRC),
Subject:
Confirmation of Action (1 page) 23.
5/1/80 Letter to J. P. O'Reilly (NRC) from W. R. Cartwright (VEPC0),
Re: Licensee Event Report No. LER 80-027/99 X-0, NRC Accession Nos. 8005080491 and 8005080493 (5 pages) 24.
3/17/78 Letter to J. P. O'Reilly (NRC) from W. P. Stewart (FPL) Re:
Licensee Event Report No. LER No. 78-017/0lT-0, NRC Accession Nos. 8003030889 and 8003030892 (3 pages) 25.
5/15/78 Report re: Crystal River 3, Florida Pcwer Corporation, Report No. 50-302/78-10, NRC Accession No. 8002280893 (4 pages) 26.
7/11/78 Report re: Crystal River 3, Florida Power Corporation, Report No. 50-302/78-16, NRC Accession No. 8003040901 (6 pages)-
27.
Undated Page 5 of NRC Inspection Report No. 50-3d2/78-21 which closes the Outstanding item related to loose parts (1 page)
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NUCLEAR REGUt.ATORY COMMISSION 6
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FleWMY e 4 E0 Docket Ho. 50-338 e
'ir. W. L. P rof fi tt Senior Vice President - Power 1
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Virginta Electric & Power Cogany b
P. O. Box 26665 ff Richcond., Virginia 23261 C ;-
Dear Hr. Proffitt:
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Subject:
Safety Evaluation Report for the Steam Generator Inspection and 7{
Maintensnee at the North Anna Power Station Unit No.1
,4 di We requested on Noves:bar 30d9799 that you submit a report on the first refueling i,
steam generator inspection at North Anna, Unit 1.
g Your submittal, dated December 10, 1979, for the North Anna, Unit 1 steam generator h
inspection has now been reviewed and evaluated. Our Safety Evaluation Report Rt regarding this nstter is providad in the Enclosure to this letter. '
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It is our conclusion that tha steam generator inspection at North Anna. Unit 1 was adequate to establish the present condition of the steam generators. Also, the C
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preventive mintenance (tube plugging) performed as a result of inspection provides D
reasonable assurance that the Worth Anna, Unit I steam gerterators can continue to operate without igairing the health and safety of the public.
- h@t qs Finally, we conclude that the steam generator inspection and maintenance at M. th 3$
Anna, Unit i has been perforand in a canner consistent with the Cemissica's 2
requirc aent for uaintaining occupational exposures as low as reasonably achievable Q
( ALMA).
i.Q Sincerely W
M gf' y'W A. $chwencer, Chlaf I jy Operating Reactors Branch #1 fA i
Division of Operating Reactors Q
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Enclosure:
Safety Evaluation Report N'
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a SAFETY EYlJ.UATION REPORT i-
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'FOR
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QF OF THE STENi GENERATORS m
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.g VIRGINIA ELECTRIC AND POWER COMPANY d $-
DOCKET NO.
50-338 9,.,
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BACKGROUND
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The North Anna Power Station, Unit No.1 (North Anna,1) shutdown on Septecbei for its first refueling outage after beginning comercial operation on June 6
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Prior to the refueling outage, the Virginia Electric and Power Co= party (the 1-
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had detected a minor prictary to secondary steaa generator leak of approxinite' AM to:three gallons per day. As required by tha Technical Specifications, an in'
- Q of the stcan generators for North Anna Unit I was perfornad during the first Q
outage.
WW The results of the steam generator inspection at North Anna, Unit I were disci a ceeting on Hovember 30, 1979 with the licensee, the licensee's consultant ai Qi' staff and are documented in a ceoting seansry, dated Dece6er 19,1979. By h iw dated Dececber 10, 1979, the licensea submitted its stean generator inspectici
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and resultant caintenanco and cleanup procedures for the steaa genarators at I
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An na', 1.
Our review and evaluation of the Itcensee's inspection and maintenal actions is provided below.
DISCUSSION I
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The major findings of the steam generator inspection were (1) through wall del a;p near the tangent to the U-bend of two rcw 1 tubes in steam generator C which 1??
the s=411 leaks prior to shutdown and (2) support plate / tube intersection cor Jif,'q and possible ligament cracking, indicative of an early stage of denting.
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Approximately 1070 tubes total in all three generators were inspected using a l W T#
eddy curre'nt prode. With the exception of the two rcw 1 leaks and one tube wi Ef could not pass the 700 mil probe (all in steam generator C), no indications of W
defects were observed.
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Mditional inspections of row I and row 2 tubes were performed using 100 ml differential and absolute probes to supplecent informtion gained froa tha WO GZ probe in the U-bend region.
Almost all re,v 1 tubes were inspected using one or both of these probes.
I Most rcnv 2 tubes in steam generators A and C were similarly inspected, with the result that no additional U-bend indications wero. observed.
A photographs takan during the inpsection indicate no detectable support plate flow slot closure (hourglassing).
To preclude further U-bend leaks and patential ruptures in the row rel ated.
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tubes the licensee plugged all row I tubes in the three steam generators.
6L In addition to the 400 KHZ inspections, a 7.5 KHZ prche was used in a total of M
910 tubes in all three steam generators to detect indications of support plate corrosion and possible Ifgament cracking.
V cne third of the tubes so inspected, and appear to signal the very early stag C
of the denting phenocenon affecting other plants.
M C) which failed to pass a 700 mil probe did pass a 650 all probe.Also, the one tube (st
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that denting at North Anna,1 is at a very early stage.
As a preventitive ceasure.
the licensee plugged this tube and its af rror icage on the same(hot leg) side.
,y A review of the plant chemistry data by the ifcensee and its consult:nt showed that W[
a major discharge of resins from the condensate polisher into the stem generators 1$
had occured in Febraury 1979.
The licensee has concluded that the ion-exchange resins decccposed in the steaa generator operating envircracnt producing sulfuric G
plate inte,rsections. acid which in turn led to cagnitite formation within the crevices at the t D
h3 The licensee plans a program to stop this support plate corrosion by boric acid
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treatment during the cycle 2 startup's objective is ffollowed by residual treatm id further deterioration.
The licensee or the boric acid to chtaically combine with the corrosion product magnitite to form borasite, effectively sealing
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the corrosfon sites.
t The licensee has also connitted to install inspection ports in tne flerth Anna 1 R
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steaa generators during the second refueling cutage. These ports uill be stallar to those installed at the Surry Pcwer Station Unit No.1 and lio. 2
$71 and will allow fnspection of the upper tube support plate'and tuba 0-bends.
Q EVAL.UATION y-The two row I U-bend tangent point defects at North Anna 1 are similar
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to those observed recently at Trojan and, icost Ifkely at Farley, Unit 1.
Detectable support plate flow slot hourglassing has not been observed at any of j$
these units and, thus, these U-bend defects are not considered to be denting
%gLi related.
Ve find that plugging all row I tubes at North Anna 1 is a conservative G
ceasure in precluding future leaks or potential tube ruptures due to U-bend defects dM of this type. To date all defects of this type have been confined to rcw 1 tubes 4
M only.
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_4 The occurrence of denting, even in its earliest stages, had not been Q
anticipated so early in the operating life of North Anna 1, based on MW experience at other plants using secondary water all-volatile-treatment D
and fresh water condenser cooling water.
We find that the licensee has A
ected in an appropriate manner to identify the cause of the early MQD ragnitite formation on the tube support plates and has provided a satisfactory ML explanation. The licensee plans to icplement a program of boric acid
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}f treatnent in an attergt to step further magnitite fortation..
It is f.n our belief that this progran can be fepleranted without adversely affecting BM the corrosion resistance of exposed surfaces of the stean generator internals.
4cwever, regardless of the success of the licensee's prograa to stop cagnitite 4@
Y formation, we concluda on the basis of the inspection results that the decree 3:M of denting is too minor to be considered a significant safety issue at this time.
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de cenclude that the s' team generator inspection at North Anna 1 was adequate to establish the conditicn of the steam generators. Also, we find that the "M
Ifcansee has f6pleraented conservative maintanence and corrective actions
- occensurate with the findings of the steam generator inspection, and that l
- entinued operation of the North Anna 1 steam generators will not icpair the health and safety of the public.
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)uring the recently cocpleted first inservice inspection of the steam generaturs f
it North Anna 1, the Ifcensee perforced about 2500 ed@ current tests on the Q)f steca generator tubes. As a result of these tests, 284 tubes were plugged in the
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three stets generators.
the licenses selected and used several techniques developed by industry for
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siintaining radiation exposures-as-low as reasonably achievabic (ALARA),
( -i for the tube inspection and plugging. For the eddy current testing on the iteam generator tubes, remote equipment was used which alicwed the cperators M;.Q
- o perform most of the tima consuming task in a lower radiation field than g7 eculd otherwise have been possible. Also, tecporarf shfolding was Installed im j
- nside the steam generator channel head to further reduce exposures to the ag ecrators.
In order to further reduce exposure tice, opticum operator
%g iroficiency was developed by using a cock-up to train the operators regaged in those tube inspection and plugging procedures involving radiation Qp%
(yyM ixposure.
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Is a result of these dose reduction techniques, the operators pe-foruing the
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- ube insection and plugging received 68 raan-rem of collective occupational i lose.
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64;W tased upon the licensee's approach and the level of occupstional exposure wCM rxperienced, we conclude that the steam generator inspection ano usintenance iO!d it North Anna 1 has been perforced in a manner consistent with the Con:ission's MS equiremnt for natntaining exposures as-Ics-as reasonably achievable (ALARA).
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