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JAN 181977 MEMORANDUM FOR:
D. Eisenhut, Assistant Director, OT, DDR FROM:
L. C. Shao, Chief. Engineering Branch, OT, DDR
SUBJECT:
TECHNICAL SPECIFICATIONS AND ASSOCIATED BASES FOR STEAM GENERATOR TUBE SURVEILLANCE N
REFERENCE:
Memo from J. F. Stolz to D. Ross and J. Knight, November ll, 1976,on the subject matter The Engineering Branch, Division of Operating Reactors, has reviewed the proposed changes in the additional reporting requirement in the Westinghouse Technical Specification 4.4.5 and the basis for the change, with respect to the subject matter in the referenced memo.
v We have concluded that any change at this moment is premature and does not contribu.te substantively to the protection of public health and safety.
There are three tasks currently being conducted:
(1) Regulatory Guide 1.83 is currently being revised to incorporate the results of a statistical study on the inservice inspection sample size and the plugging limits, and operational experiences of steam generators.
(2) The Applied Statistics Group in the Office of the Technical Advisor to the Executive Director for Operation, has been con-
. ducting a statistical study on the inservice inspection sample size and the adequacy of current tube plugging criteria.
(3) Based on a request from NRR, RES has sponsored a confirmatory research program at Pacific Northwest Laboratory (PNL) to deter-l mine the burst strength, the leakage rate, the collapse strength, and the cyclic strength of steam generator tubes with various forms of degradation.
Results of this program will be used to evaluate the current allowable leakage rate and plugging limits in the Technical Specifications.
(4)
D. Ross' group is re-evaluating the accident and transient i
analysis to determine the pennissible number of failed tubes.
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D. Eisenhut JAN 181977 I
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These tasks represent the total substantive in-house effort to pro-duce, a set of reasonable and enforceable quidelines with regard to the assurance of steam generator tube integrity. Any additional reporting requirements can be decided when results of the above mentioned tasks are completed and ' documented.
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L. C. Shao, Chief Engineering Branch Division of Operating Reactors
Enclosures:
Memoranda by L. L. Kintner cc:
V. Stello, Jr., D0R ie R. Heineman, DSS J. Knight, DSS L. Shao, D0R l
J. F. Stolz, DPH S. Pawlicki, DSS l
R. Bosnak, DSS R. Stuart, D0R L. Frank, SD C. Cheng, D0R F. Almeter, D0R l
B. Liaw, D0R
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Contact.
B. D. Liaw 28060 l
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SEP 13 1976
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l Note For:
J. Stolz, Chief, Light Water Reactors Branch No.1. DPM l
j From:
L. L. Kintner, Project Manager, Light Water Reactors Branch No.1, DPM DECISION BY APPEAL BOARD RE - PRAIRIE ISLAND UNITS 1 AND 2 (ALAB-343),
SEPTEMBER 2, 1976 The subject decision uses a term on page 28 that indicates the board may have misinterpreted the technical specifications proposed by the staff (Maccary,AppendixB).
It could be significant in light of its finding i
on page 73 that these specifications appear to be acceptable.
Page 28 and page 26 seem to imply that if four or more tubes'have
, eddy current measurements of penetration greater than 50% they would.
be " reportable" to the Comission, as recomended in Regulatory
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V Guide 1.83, Section C.7.d.
The proposed technical specifications for P-rairie Island would not require such reports unless "l% of the inspected tubes" are defective.
This would mean that up to 66 tubes would have penetrations greater than 50% in order to be a " reportable event" as defined by Regulatory Guide 1.16. My memo to Karl Kniel dated December 9,1975, provides further evaluation of the technical specifications as proposed by Maccary testimony.
I suggest that the term " reportable defect" as used on pages 26 and 28 l
should be thought of as a "measureable defect", or a " detectable defect".
L. L. Kintner, Project Manager Light Water Reactors Branch No.1 Division of Project Management s
l cc:
D. Vassallo o. Knight D. Ross J. Scinte l
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