ML20023A525
| ML20023A525 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Point Beach |
| Issue date: | 04/18/1975 |
| From: | Lear G Office of Nuclear Reactor Regulation |
| To: | Schroeder F Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19302F297 | List:
|
| References | |
| FOIA-82-309 NUDOCS 8210070191 | |
| Download: ML20023A525 (3) | |
Text
y UNITED STATES NUCLEAR REGULATORY COMMISSION Q
WASHIN G Toti. D.
- c. 2055s
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APR i s B75 F. Schroeder, Acting Director, Division of Technical Review TECHNICAL ASSISTANCE REQUEST NO. ' ORB-3-54 Your assistance is requested in the following:
PLANT NAME:
Point Beach Unit 1 DOCKET NO.:
50-266 RESPONSIBLE BRANCH:
OPERATING REACTORS BRANCH #3 (ORB 3)
CONTACT:
J. Wettore (phone 7872)
'u d
TECHNICAL REVIEW BRANCHES: Materials Engineering Branch, g p' '
h TARGET COMPLETION DATE: May 7
734 p
DESCRIPTION OF REQUEST:
Background
- a.
Tube Rupture Incident at Unit 1 On February 26, 1975 Point Beach Unit 1 experienced a steam generator tube leakage Ng' incident.
The abnormal Occurrence Report
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is enclosed (Enclosure 1).
~
Electric Poser Co=pany (NEPCO),the licensee, subsequently perforced eddy current inspec-
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tion of approximately 99's of the tubes in both steam generators, and plugged all tubes Q
wasted greater than 30*6.
After OIGE completed k~
a review of the licensee's tube inspection nd T y and the planned repairs, a report was prepaled N.0
\\
by OIGE (Enclosuro 2) in which it was concluded d')#
that OISE had no technical c'oncerns regarding A
p,g 4-the resumption of operations at Point Beach 1
Unit 1 following the completion of the repairs.
C 1
0 The unit was returned to service on April 5, f
1975.
[
Although OISE and DRL both had concluded that no immediate licensing action was needed to control Unit 1 operation, it was considered prudent to obtain. pertinent data to develop a basis fer any future licensing action which
'niight be required. We requested WEPCO to
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76 #6 (i PDR FOIA LONG82-309 PDR
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F. Sc'hroeder supply information relative to' Point Beach Unit 1 steam generator tube history (Enclosure 3). The specific information requested from WEPCO was essentially the same information identified in a March 20, 1975 memo to Karl Goller from R. R. Maccary (Enclosure 4).
In their submittal dated April 7,1975 (Enclosure 5), WEPCO has provided a response to our request..
b.
Technical Specification Change In response to our letter of July la,1974, which attempted to implement provisions of Regulatory Guide 1.83, WEPC0' submitted a proposed amendment (Enclosure 6) of their license to provide "an acceptabic program for inservice inspection of steam generator tubing".
Request Please review the information in the enclosures in the context of the steam genera' tor tube leakage incident of 2/26/75 and current regulatory requirements regarding steam
, generator tube integrity.
Specifically, jin vie,w of:
(1) the steam generator water Ichemistry history; (2) the water chemistry control currently in use; (3) the tube cor-lrosion observed by inspection; and (4) the
' requirements of Regulatory Guide 1.83,.please 9etermine the acceptability of the proposed
Technical Specifications for steam generator tube inservice inspection (Enclosure 6) submitted by WEPCO on August 30, 1974.
In evaluating-these proposed Technical Specifications please address, in particular, the acceptability of: (1) the inspection frequency; (2) the_ tube plugging criterion; (3) the number of tGbes inspected per lispection interval; and (4) the number of ;
defective tubes found which define an abnorhal occurrence.
In a'ddition, please identify any special require-ments which you believe 'are necessary to provide, assurance that stean generator tube integrity will be maintained.
In this rega'rd, we request your identification of requirements for the following:
steam generator water _ chemistry; primary to secondary Icak rate limits; the maximum time interval between now and the next
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3 4
J
.i F. Schroeder -
4 tube inspection; limits and measurement procedures for the rate of tube wastcage.
Please provide the results of your reyiew in a written safety evaluation by May 15, 1975.
t l
, j, J
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George Lear, Chief Operating Reactors Branch #3 Division of Reactor Licensing
Enclosures:
1.
Licensee Event Report
. No. 50-266/75-4 2.
IE Inquiry Report No. 50-266/75-01 3.
Letter to WEPCO from j
G. Lear dtd 3/24/75 4.
Letter to K. Goller from R. R. Maccary dtd 3/29/75 5.
Steam Generator Chemistry and Inspection Information, Point Beach Unit I dtd 4/7/75 6.
WEPCO Request for Technical Specification Change dtd.8/30/74 cc:
J. Wetmore G. Lear D. Eisenhut i
K. R. Galler i
T. J. Carter '
l S. A. Teets
.J. Knfght S. Pawlicki L. Frank L. Knitner-K. Knielw TR Bianch Participating 4
l J.
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