ML20125E382
| ML20125E382 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1980 |
| From: | Noonan V Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002120103 | |
| Download: ML20125E382 (3) | |
Text
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ll MMORANDuM FOR: R.; W. Reid, Chief, Operating Reactors Branch #4
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FROM:
V.:5.Noonen[thiefEngineeringBranch 4
Division of Operating Reactors
SUBJECT:
THREE-MILE !$ LAND UNIT #1 - AMEN 0 MENT OF THE TECHNICAL
" %,, SPECIFICATIONS To FACILITY OPERATING LICENSE NO. OP 1-(TACS#10793) l Plant Nese Three Mile Island Ustt No. 1;,
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, Licensing Stages Operating Plant
'l 9 Docket Number: 50 289 Documents Revieweds a.
Metropolitan Edison Co.--Letter from Stibert/Comon-
- wealth to ETED dated December 7,1979.
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Three Mile dsland Nuclear Station Unit 1.-Reactor Con-d.,
tainment Seilding Structural Integrity Test Report Mf' prepared by Gilbert Associated, Inc., June 14, 1974.
N and Project Manager Requisting Assistance:
DRB D. C. Dilanni, R. W. Re Operatinq Reactor Branch Involved: Engineering Branch l
Descript' on of Request: TAC 3 #10793 i
t Review Status: Complete
. The Engineering Branch, DivisienMapecating Reactors, has reviewed the infor-i action submitted by the Metropolitan Edison Company in the Cocuments listed l
above proposing to eliminate the temporary ring girder surveillance program and to allow future inspections of the tendon anchorage assemblys to be performed in conjunction with the normal containment structural surveillances t
Background _
In our~ previous memorandum dated November 28, 1978 regarding the temporary ring girder surveillance progran and the Tendon surveillance, we made the following recoamendations:
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p 1; upon the cog letion of the repairing work of the ring girder, the temporary surveillance tests of the ring girder can be eliminated.
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NRC Form 318 (2 76) NRCM 02040 fr u.s. aovanusN T rnin r N o op rie s toe.eu-na w,a f
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Visual inspections of the ring girder be performed by the licensee and its results reported to NRC in accordance with the recocmendations of the Regulatory Guide 1.35.
The licensae proposes as stated in the first document that the overall visual inspection for cracking and anchorage conditions during the ILRT be eliminated citing that this requirement has been removed from Regulatory Guide 1.35 i
Revision 3.
Since the Revision 3 of the Regulatory Guide 1.35 modifys the i
same recomended procedures from that of the Revision 2, concern was raised with regard to the technical basis of modifying the regulatory position C.3:
specificalln the technical basis of removing the sentence "The technical basis ofOmdE Gif@. scheduled during integrated leakage testing while the i
contitinment is at its maxistan test pressure."
Discussion Our review of the above documents, Regulatory Guide 1.35 both Revision 2 and 3, and Appendix J to 10 CFR Part 50, reveals the following t
1.
Appendix J " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactor" sets. forth the requirements for the containment leakage rate testing. The required " Type A tests" are to measure the primary reactor containment overall integrated leakage rate (1) after the containment has been completed and is ready for operation.(ISIT), and (2) at periodic intervals thereafter. The pressure fgGJWFor Is1794Ja deC6e Wu a f/m'n t'Pd' > r peak containment internal pressure related to the design basis accident '
the Acm.prequired for periodic tests shall not be less than 50 percent of tha pressure used in ISIT. A general inspection of the accessible interior and exterior surfaces of the containment structures and components shall be
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performed.
2.
Although the details of the containment inspection have not been specified in the Appendix J, reasonable engineering judgment should enable the engineer to pick up what and where to monitor the structural behavior during the tests.
Sound judgment has been demonstrated by METED during the TMI-l's ISIT, performed in 1974. Instrumental measurements and visual inspections were utilized to i
measure the displacements, strains, concActe conditions and crack patterns at preselected locations - at the outside surface of the containment and the tendon anchorage zones.
3.
Regulatory Guide 1.35 Revision 3 adds the recommendation that the exterior surf ace of the containment should be visually examined for cracking, spalling, and grease leakage while deletes the sentence "The visual examination of the concrete should be scheduled during integrated leakage testing while the con-tainment is at its maximum test pressure." Apparently, this has been mis-interproted as that the overall inspection for cracking and anchorage conditions
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during the ILRT would be eliminated as a require::ent (Document a.).
It should be noted that ILRT is required by the Appendix J.
The visual inspection is only one of measures to detect the early signs of deteriora-
.I-tion of the containment and the associatedecost is rather minimal.
f 4.
Reasons have been cited:
(a) ISIT was tested at higher pressure than the peak accidentalpressure without any sign of.. apparent structural deterioration,
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' {b) pcisEILR_testsJnd.icate no.si,cJn Oflelerioration;< thus, the' visual' '
Inspection of the concrete during I[RT could be eliminated. Based on these rationing, we may not need any monitoring during normal operations because the interior pressure is much lower than that during the ILRT.
J 5.
The cost of performing a visual examination of the concrete during normal 1
operation or during ILRT should be the same.
l 6.
The " maximum test pressure" may have been construed as the calculated peak containment internal pressure related to the design basis accident, thus the tendon surveillance must be performed when the plant is in a shut-down condition.
Conclusion Since the periodic integrity leakage rate tests are required for all water cooled reactors in accordance with Appendix J and a general inspection of the containment shall be performed to evaluate the structural conditions which may contribute to the failure in meeting the acceptable leakage criteria, the visual concrete inspection, presumably, will be performed during any ILRT. The visual conditions of the tendon anchorage zones may be considered as a by-broduct obtainable from the ILRT and can be used to evaluate the tendon conditions. The visual inspection as recoramended in Regulatory Guide 1.35 Revision 3 should not be construed as the basis for eliminating the inspection during ILRT. It probably should be interpreted
.that the schedule of the tendon surveillance does not have to coincide with that of
the ILRT.
V. S. Noonan, Chief Engineering Branch Division of Operating Reaci: ors cc:
D. Eisenhut, 00R
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