ML20037A455
| ML20037A455 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 03/17/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20037A457 | List: |
| References | |
| NUDOCS 8001310525 | |
| Download: ML20037A455 (5) | |
Text
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i MAR 171977 0]
I MEMORANDUM FOR:
K. R. Coller Assistant Director. OR DOR FRON:
D. G. Eisenhut. Assistant Director. OT D0R
SUBJECT:
OCONEE 1. 2. AND 3 TECHNICAL SPECIFICATIONS FOR STEAM GENERATOR INSERVICE INSPECTION Plant Name: Oconee 1, 2. and 3 1.icensing Stage: OL Docket No: 50-269/270/287 j
Branch and Project Manager Pequesting Assistance: ORB-1. D. Neighbors Operating Reactors Branches Involved:
Engineering Branch
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Renuested Completion Date: March 1,1977 Description of Request: TAC No. 6463 Review Status: Awaiting Response The Engineering Branch Division of Operating Reactors. has reviewed _,._.___.M
._ Duke Power Company's request dated November 30.~1976'foF a license i
amendment for the Oconee Nuclear Station to incorporate requirements concerning the operability and inservice inspections of steam nener-ators. He have found that the proposed technical specifications have several major conflicts with the Standard Technical Specifications.
Our cornents along with some of the major deviations are listed in Enclosure A.
Enclosure B is a copy of the most recent Standard Technical Spect-i fications proposed by the Engineering Branch.
It is suggested that these Standard Technical Specifications be forwarded to Duke Power Company and that they modify their proposed specifications to conform with the Standard Specifications placing particular emphasis on the conraents in Enclosure A.
Any deviation fmm the Standard Technical Specifications will require justification.
D. G. Eisenhut. Assistant Director for Operational Technology Division of Operating P.ea-tors
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CONTACT:
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ENCLOSURE A I
COMMENTS ON OCONEE UNITS 1, 2 AND 2 PROPOSED TECHNICAL SPFCIFICATIONS FOR STEAM GENERATOR f
INSERVICE INSPECTION 1.
Table 4.17-1 which specifies steam generator tube sample size, inspection result classification, and the corresponding action y
required for each sample inspection has several discrepancies with the standard technical specifications:
If the results of the first sample inspection fall in the C-2 a.
category, the corrective action should be the plugging of the defectivetubesandinspectionof(%additionaltubesinthat steam generator. Where N is the number of steam generators in the unit, and n is the number of steam generators inspected 4
during an inspection, b.
If the results of the first sample inspection of a steam gener-ator fall in the C-3 category, the corrective action should includeinspectionofalltubesiijthesteamgenerator, plugging of defective tubes, and inspectior of an additional (% of the
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1" tubes in eacn other steam generator.
Corrective actions corresponding to results of second and third c.
sample inspectiors have not been specified in the table. These actions should be specified in accordance with Table 4.4-2 of the standard technical specifications. Guidance for subsequent (second and third) sample inspections as stated in paragraph 4.17.1,b of the proposed technical specifications is unacceptable.
The sample sizes required during each sample inspection are clearly specified in Table 4.4-2 of the standard technical specifications.
Deviation from the specified sample sizes will require a statistical analysis justifying the proposed sample sizes.
2.
Paragraphs 4.4.5.2,,b, c and d of the standard technical specifications should be included under paragraph 4.17.1,b of the proposed technical specifications.
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Paragraph 4.17.2,b should read the same as paragraph 4.4.5.3,b in 3.
the standard technical specification.
Paragraph 4.17.2.c should also specify that unscheduled inservice inspections shall be performed on each steam generator in accordanc 4.
with the first sample inspection during the shutdown subsequent to:
A seismic occurrence greater than the Operating Basis Earthquake, a.
A loss-of-coolant accident requiring actuation of the engineered b.
safeguards, or A main steam line or feedwater line break.
c.
Justification for the proposed 40% plugging limit must be provided 5.
in accordance with Regulatory Guide 1.121.
The term " unserviceable" used in the definition of plugging limit 6.
must be defined.
The definition of defect should read as follows:
7.
Defect means an imperfection of such severity that it equals or excef the plugging limit. A tube containing a defect is defective.
8.
The basis should state:
Cracks having a primary-to-secondary leakage less than the speci-fied limit during operation will have an adequate margin of safety a.
to withstand the loads imposed during normal operation and by postulated accidents. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking :.abes will be located and plugged.
Cases when the results of any steam generator tubing inservice b.
inspection fall into category C-3 will be considered by the Comission on a case-by-case basis and may result in a requirement for analyses, laboratory examination, tests, additional eddy current inspection, and revision of the Technical Specification, if necessary.
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The subject of operability of steam generators as discussed in.
sectiont. 3.4.5 and 4.4.5.6 of +,he standard technical specifications should be addressed.
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