ML20079K316
| ML20079K316 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 12/29/1982 |
| From: | Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| Shared Package | |
| ML20079F227 | List: |
| References | |
| FOIA-83-363, TASK-PII, TASK-SE SECY-82-502, NUDOCS 8301070163 | |
| Download: ML20079K316 (3) | |
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SECY-82-502 December 29. 1982 I E e
POLICY ISSUE
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(information)
For:
The Commissioners Frcm:
William J. Dircks Exe'cutive Director for Operations Subjecc:
Status of Certain Non-Hearing Issues on TMI-l Purcose:
To inform the Ccemission of the status of staff review for TMI-l or the auxiliary feedsater. header problem and the make-up nczzle cracking prcblem that occurred on several B&W plants; and the steam generator tube problem on TMI-l as directed by the Commission in its Order dated July 16, 1982 (CLI-82-12).
Backcround:
By Order datec June 30, 1982, the Atomic Safety and Licensing Appeal Board for the TMI-l restart proceeding requested authorization frem the Ccemission to hear three issues cua sconte.
These issues relate to:
(1)thepos-sible distorting of the auxiliary feedwater header, (2) whether there has been any cracking in high pressure injection 3r.make-up system nozzles or thermal sleeves and (3) the repair of the corroded steam generator tubes.
By Order dated July 15,1982 (CLI-82-12), the Commission denied the Appeal Scard's request but directed tne staff to thoroughly examine these issues and provide its analyses l
and findings to the Commission prior to the time the Commis-sion is to make its decision on the restart of TMI-1. The follcwing is the current status of the three issues.
The requested staff findings with respect to the first two issues are reported below.
The staff review and findings regarding repair of steam generator tubes will be completed after het functional testing, now scheduled for late
' April 1983.
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Contact:
R. Jacobs, NRR X27471 XA Copy Has Been Sent t., PDR
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Discussion: The auxiliary feedwater header problem identified by the Appeal Board refers to distortion of the internal auxiliary feedwater header experienced at Davis-Besse, Oconee 3 and Rancho Seco. The internal header, wtich is installed in Davis-Besse, Rancho Seco, Oconee<3, Midland 1 and 2 and TMI-2, is rectangular.and encircles the tube tuncle. The r'est of the B&W plants including TMI-1 use an external feedring with seven nozzles penetrating the steam s'enerator shell and shroud.
Hence, this problem is not applicable to TMI-1.
The corrective action completed at the affected B&W plants involved stabilizing the internal header and installing an external feedring similar to that used at TMI-1.
The make-up nozzle probism in B&W plants refers to cracking that occurred in the makeup. nozzles to the reactor coolant system cold legs of four of the B&'d plants. The Commission was informed of the status of this problem in SECY-82-186 dated May 7,1982 and SECY-82-186A dated July 23, 1982.
The problem appeared to be related to the conditi~on of the nozzle thermal sleeve.
In each instance where nozzle cracks were detected, the associated thermal sleeve had been loose or in the case of Rancho Seco, the sleeve was missing. All four HPI nozzles were inspected at TMI-1 and no degradation was detected.
Additionally, it was confirmed that the thermal' sleeves were in place. Hence, no additional short term action is considered necessary for TMI-1 prior to restart. A B&W Owners Group task force is pursuing whether any additional generic action is necessary for the B&W plants. The~ task force final report is due to be completed in January 1983.
It is expected to recommend augmented in-service inspection in B&W plants to provide long term assurance against further degradation. The staff agrees
' with this reccmeendation and will be reviewing each licensee's submittal when received.
With respect to the steam generator. problem,'the staff's review is continuing.
On October 13, 1982, the staff issued a safety evaluation supporting our finding that GPU may-proceed with repairs of the steam generators, but that NRC approval was necessary before any subsequent operation.
GPU is approximately midway through the kinetic expansion program with cleanup of debris,' plugging of approximately 800 tubes (354 tubes previously plugged) and steam generator testing required to complete the repairs. Additionally, e
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, ' GPU plans to mill off the top end of the tubes where they protrude through the upper tubesheet since a number of these tube ends have been breaking off frca the expansions due to defects in the heat affected zone of the seal weld.
GPU anticipates completing the above repairs and cold testing by mid March 1983.
Following the, repairs, GPU may conduct desulfurization of the reactor coolant system, if determined to be necessary, to be followed by hot functional testing which GPU has targeted for completion by late April 1983.
On December ~,, 1982, G?U submitted their safety evaluation concluding that TMI-1 can be safely returned to service once the repairs and associated activities have been completed satisfactorily. The staff position as stated in SECY-82-35A dated July 19, 1982 is that unreviewed safety questions are.
involved and a license amendment is needed to modify the Technical Specifications before the steam generators can be declared " operable". The staff intends to complete its review and issue its final safety evaluation after ccmpletion of steam generator hot testing.
kAk,J.Dircks L
William r
Executive Director for Operations O
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