ML19338F119
| ML19338F119 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/02/1980 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TLL-500, NUDOCS 8010070542 | |
| Download: ML19338F119 (6) | |
Text
-
o Metropolitan Edison Company Post (>fice Box 480 g
Middletown, Pennsylvania 17057 717 9444041 Wnters Direct Dial Number October 2, 1980 TLL 500 Office of Nuclear Reactor Regulation Attn:
R. W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Status of SER Open Items Reference 1:
T. M. Novak's letter to R. C. Arnold of August 11, 1980 Reference 2:
D. G. Eisenhut's letter of September 5, 1980 to All OL and CP Plante this letter is in response to your letter of September 4, 1980, which requested schedules foi providing information concerning open items related to Order Item Nos. 1, 2, 4, 5 and 8.
The enclosed table summarizes the remaining significant open items. As noted in the SER, some additional items will remain open awaiting completion of procedures, tests, or technical specifications.
The status of these items is not addressed in this response.
For the Order Items mentioned above, there are thirteen open items that can be categorized in the following three groupr:
i A.
Items that have been conceptually described,and detailed information is needed only for confirmation.
(Five items:
4, 8(2.1.4, 2.1.8.a, 2.1.8.b, and Add'l. 4).
Several of these items are long-term implementation items.
Schedules have been provided in the enclosed table.
B.
Items that are pending NRC action or review.
(Four items:
8(2.1.3.a, 2.1.3.b, 2.1.9 and Long-Term 2).
Item 2.1.3.a requires that an under-standing of the NRC's continuing concerns be made available to the Licensee. The remaining three items are related to Inadequate Core Cooling, which are the subject of hearing testimony filed September k( y
15, 1980 in support of our position.
C.
Items to be responded to by October 15, 1980.
(Four items:
2(IEB 79-05B-1), 5, and 8(2.1.6.b and 2.1.7.a).
8010070 M
[
Me!rc001!3n Ed son Company >S a MeTter Cf :he Gener3! Pubhc L'N Pes Sys!Gm
i R. W. Reid TLL 500 With regard to Order Item No. 7, we expect to provide the majority of the information requested by Reference 1 on October 6,1980. We note, however, that.our financial position continues to be dependent on regulatory actions by state utility regulators, and that analysis of our financial position has been changing and can be expected to change further.
It is, therefore, not likely that submittal of the requested information by October 6, 1980 will be sufficient to close this item.
It is, for this reason that we have proposed that the issue of financial qualification be taken up as the last issue in the restart hearings.- We will continue, as we~have in the past, to provide financial updates as they are requested.
Although not the subject of your letter, there are additional open items in Order Item 3 (Emergency Planning). We received your letter of September 9, 1980 on September 23, 1980. This letter asks for responses to twenty-three additional questions on emergency planning issues. Since the SER was previously complete in this area, we do not anticipate delays in proceeding to hearing while these latest questions are being responded to.
We will respond to these questions within the requested forty-five days from receipt. To our kn6wledge, we have responded to all questions regarding management structure.
We are not aware of any management issues which require our response in order to proceed with the hearing activities associated with Order Item 6.
l Finally, it should be noted that several of 'these items are still the subject l
of f ;ernal NRC criteria development as evidenced by Reference 2.
This document presented new views and requirements on many of the items covered by Order Item 8, and modified the implementation schedule for many more of these items.
To conclude that we have been unresponsive to firmly established requirements is therefore inappropriate since many of the requirements are not yet firmly established and continue to fluctuate.
It would also be inappropriate to require l
as a condition for restart, implementation by TMI-l of new views and requirements on a schedule different than other operating reactors. The regulatory l
criteria that should form the basis for TMI-l Restart should be those underlying
)
the August 9,1979 Order so that judgements concerning the necessity for and sufficiency of the improvements made to TMI-l for Restart can be made. With that basis, conclusions regarding TMI-l operational safety and management have an identified frame of reference that is in keeping uith the requirements for all operating reactors. Subsequent evolution of regulations can and should be the subject for review between the NRC staff and any licensee, but these efforts
?
for TMI-1 should not be part of the considerations for restart.
I j
Sincerely, 1
Director, TMI-l HDH:EDW: hah Enclosure cc:
J. T. Collins B. J; Snyder B. H. Grier D. DiIanni H. Silver 1
/
I
CHOUP A, B, AND C SER OPEN ITEMS ORDER ITEM NO.
OPEN ITEM DESCRIPTION STATUS /SCllEDULE 2
Analysis of Anticipatory This analysis and resulting guidelines have been re-(IEB 79-058 Item 1)
Filling of OTSG viewed by us in draft form and will be provided in final form by October 15, 1980.
4 Design Detail for the New This system will be used to mitigate a fuul handling
+
Fuel llandling Building accident and is not needed during power operation.
8 Ventilation System This modification is not scheduled to be installed until the first refueling after reatart. A conceptual description was provided in Amendment No. 18 to the Restart Report. Design detail will be provided by June 1981.
5 Plans for Storage of Low Space for storage of TMI-l radwaste has been alloted Level Radwaste Prior to in the waste storage ared to be provided for TMI-2.
j Shipment This facility is expected to be completed by August 1981.
Additional details will be provided by October 15, 1980.
i 8
Justification for Safety NRC has not documented the naturu of their concern!
(2.1.3.4)
Valve Position Monitors therefore, we are unable to respond appropriately.
/
8 Evaluation of the Need Our position la that the inadequate core cooling guide-(2.1.3.b) for Additional Instruments lines submitted in Decembet-1979 are complete and that to Detect Inadequate Core no additional irstruments are necessary or desirable.
Cooling NRC has not yet identified to us any needed improve-ments in the inadequate core cooling guidelines.
% ORDER ITEM NO.
OPEN ITEM DESCHIPTION STATUS /SCIIEDULE S
Design Detail for the Rup-This system was conceptually described in Aamendment (2.1.4) ture Detection Isolation for No. 18.
On the basis of that information, the NRC ICCW and NSCCW should be able to rule on the acceptability of our approach and confiam that these conceptual ideas have been achieved. These will be incorporated in the detailed design at a later date.
The details of the design will be available by January 1981.
8 Study of the Need for Plant Submittal of the study has been delayed pending (2.1.6.b)
Shielding finalization of modifications to correct any probleias.
This study will be provided without definition of cor-rective measures by October 15, 1980, since the need to identify modifications has been delayed by Refer-ence 2 (see Item II.B.2). Modifications to correct any problems will be described by June 30, 1981.
8 Design Detail of kevised We have reviewed the design of the NNI and have con-(2.1.7.a)
OTSG Level Indication cluded that it is more feasible to provide new level indicators independent of the NNI than to modify the NNI.
As part of the remote shutdown panel require-monts for fire protection, new instruments meeting the single failure criteria will.be provided. These instru-ments will be installed initially as control grade be-fore restart, and later replaced with safety grade in-strusnents as they become available and plant conditions 4
3 O'RDER ITEM NO.
OPEN ITEM DESCHIPTION STATUS / SCHEDULE 8
Design Detail of Hevised permit. Conceptual design information will be provided (2.1.7.a)
OTSG Level Indication by October 15, 1980. Design details will be available Cont'd.
by January 1981.
8 Post Accident RCS Sampling Implementation of this system has been delayed until (2.1.8.a)
System Design
January 1, 1982 by Reference 2 (see Item 11.B.3).
In addition, Reference 2 has also changed the design re-quirements for the system. As indicated in Amendment 18, our effort will continue to be directod toward demonstrating that the existing sampling system (with minor modifications) can meet the NHC requirements.
Final justification will be provided by October 30, 1980.
I i
8 Design Details for the This item has been delayed until Octobor 1, 1981 by (2.1.8.b)
Long-Term High Range Reference 2.
We expect to be able to : nstall the Radioeffluent Monitors long-term effluent monitors before resterts however, equipment delivery is uncertain. In the event it be-comes apparent that the long-term system will not be available, procedures Will be p[epared to provide for effluent monitoring using the short-term moditications accepted in the SER to suppo'rt restart. A detailed description of the long-term system will be provided by May 1981.
8 NRC Review of Inadeguate As discussed in 8 (2.1. 3. b) above, we are waiting for (2.1.9)
Core Cooling Guidelines the NHC to identify any areau in which the guidelines that were submitted in need to be improved.
December 1979 4
4 e
F
- OhDER ITEM NO.
OPEN ITEM DFSCRIPTION STATUS / SCHEDULE 8
Design Detail and Analysis for The implementation of this item has been delayed to (Add. 4) the RCS High Point Vents and January 1, 1982 by Hoference 2.
We expect to be able RV Head Vent to provide a conceptual description of the RV head vents, that we were directed to install, by October 15, 1980.
Detailed design information for the entire venting system as described in Section 2.1.2.2 of the Reutart Report will be provided by March 1981. Analysis of the effects of hydrogen addition to the Reactor Building will be provided by October 15, 1980.
2 kesponsus to the NRC Letters Hesponses to the NRC letters were filed on June 30, Long-Tera dated August 21, 1979 and 1980 (TLL-285).
November 21, 1979 o
9
.