ML20004E839
| ML20004E839 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/11/1981 |
| From: | Lewis S NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Lochstet W AFFILIATION NOT ASSIGNED |
| References | |
| ISSUANCES-OLA, NUDOCS 8106150363 | |
| Download: ML20004E839 (5) | |
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NUCLEAR REGULATORY COMMISSION 5
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June 11, 1981 N
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-t-Dr. William A. Lochstet 119 E. Aaron Drive State College, Pennsylvania 16801 iss C
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g In the Matter of METROPOLITAN EDIS0N COMPANY, ET AL.
M (Three Mile Island Nuclear Station, Unit No. 2)
Dod:et No. 50-320 OLA
Dear Bill:
Since we last spoke regarding your remaining propo:cd contentions in this proceeding, various developments have led the Staff to believe that there now exist even more persuasive bases than previously existed for settlement and withdrawal of your two remaining contentions. The purpose of this letter is to advise you of our present thinking (it has proven difficult to reach you by telephone) and to request that yca contact us, either by telephone or by letter, to arrange for further discussions between us.
As to proposed Contention 2 on neutron monitoring, it has been our under-standing that you are prepareo to withdraw this Contention on the basis of certain modifications to proposed Technical Specification 3.3.1.1 which were proposed to you by the NRC Staff in a letter dated September 10, 1980 from Steve Gcidberg.
In the event that you are unable to locate that letter, a copy is enclosed. We have also discussed this modification with the licensee, who has agreed to ' support it provided that the additional proposed paragraph in 3/4.3.1 (Bases) is stricken as unnecessary. We agree that the paragraph is not necessary and have, therefore, deleted it from our proposal.
In addition, the new preamplifier for the Source Range Monitor has now been installed and that Monitor (NI-2) is now operable.
(See THI-2 Weekly l
Status Reports (2/8-14/81, 3/1-7/81, 3/15-21/81.))
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1 As to proposed Contention 3, which deals with potential leakage from the Reactor Building, we wish to advise you that we expect the licensee to commence processing of the highly contaminated water in the Reactor Building sump and reactor coolant system with the submerged decinalizer system
("SDS") and, if necessary, the EPICOR II system very shortly, following action by the NRC Staff.
Based upon our discussions with you, we believe that this forward step should provide the basis for your withdrawal of proposed Contention 3.
You have also previously stated that many of your concerns raised in proposed Contention 3 could be resolved by the issuance of the Staff's
" Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes Resulting From fiarch 28, 1979 Accident Three Mile Island, Unit 2" (PEIS).
Your contentions were written prior to the issuance of the draft PEIS. The Final PEIS (NUREG-0633) was issued in March 1981 and a copy has been sent to you.
The Final PEIS analyzes the potential for and consequences of leakage of contaminated water from the Reactor Building.
(See,e.g., Sections 2.1. 2.1, 3.4.4, 5. 2. 2.1, 5. 2.4, 7.1.4. )
Additionally, Lisa Ridgway sent you on May 5, 1981 copies of the testinony of the licensee and the NRC Staff, given in the Tlil-Restart proceeding, on the subject of monitoring wells. We trust that this testinony will prove informative.
With this statement of our current thinking as background, I believe we can now proceed to definitive discussions on your proposed Contentions 2 and 3.
I look forward to hearing from you in the near future.
Sincerely, Stephen H. Lewis Counsel for NRC Staff
Enclosure:
Letter dated September 10, 1980 cc w/o enclosure:
John F. Wolfe, Esq., Chairman Karin W. Carter Dr. Oscar H. Paris George F. Trowbridge Mr. Frederick J. Shon Atomic Safety and Licensing Board Dr. Judith H. Johnsrud Atomic Safety and Licensing Appeal Board Secretary
i September IC, 195 f'r Willia-A. Lochstet 119 E. Aaron Drin Stato Cr.11ecc, Fenasvlvania 16S31 In the !btter of 14tropolitan Edison Company, et al.
.(Three Mile Island fluclear Station Unit 2)
Docket No..'iG-320 OLA
Dear Bill:
Fer your request for infomation, dated August 22, 1980, I am advised that the Licensee will provide you data on the radiation levels for recent and future contai' ret entries.
Drawings of source range nonitoring channels are con-tainec in Section 7.8 of the THI-2 Final Safety Analysis Report (FSAD.) and in A,perdix 7A thereto.
Various engineerina drawings of the containment building at different elevations and cross-sections are contained in Secticn C.? of the FSAR.
A copy of the FSAR is available for putlic use at the 'PC local public document roon (LPDR) established at the State Library of Pennsylvaria, Governnent Publications Section, Education Buildina, Co ronrealtn and Walnut Streets, Harrisburg, Pennsylvania. You will be placed on the distribution list for receipt of the TMI Progran Office weekly status reports.
Enclosed, for discussion purposes, is a prelininary Staff response to the proposed draft nodifications to proposed technical speci'ication 3.3.1.1 which acco pa ied you-August 22 letter. The Staff is prepared to discuss this natter fortner at your earliest convenience.
Dist Sincerely.
NRC Central L PD P-
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LIMITING CONDITIONS FOR OPERATION
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3.3 INSTRUMENTATION 3.3.1 NEUTRON HONITORING INSTRUMENTATION
- 3. 3.1.1 As a minimum, the neutron monitoring instrumentation channels of Table 3.3-1 shall be OPERABLE.
APPLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION:
With only one source range neutror monitoring channel OPERABLE, a.
within 30 days either restore two source range channels to OPERABLE status or submit to the NRC, for its approval, a plan for restoring two source range channels to OPERABLE status, j
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With no source range neutron montioring channels OPERABLE, verify compliance with the boron concentration requirements of Specification 3.1.1.2 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by a mass balance calculation and at least once per 7 days by a chemical analysis and restore at least one source range channel to OPERABLE status within 7 days.
If not restored to OPERABLE status within 7 days, promptly, but not later
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than 30 days from loss of OPERABILITY, submit to the NRC, for its approval, a plan for restoring the inoperable channel (s) to OPERABLE status, With no intermediate range neutron monitoring channels OPERABLE, c.
restore at least one intermediate range channel to OPERABLE status within 7 days.
If not restored to OPERABLE status within 7 days, promptly, but not later than 30 days from loss of OPERABILITY, submit to t!.e NRC, for its approval, a plan for restoring at least one intermediate range channel to OPERABLE status.
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NEUTRON MONITORING' INSTRUMENTATION G
MINIMUM Y
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TOTAL NO.
CHANNELS CHANNELS
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FUNCTIONAL UNIT-0F CHANNELS TO TRIP OPERABLE
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Intermediate Range, Neutron Flux 5
and Rate 1
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Source Range, Neutron Flux and Rate 2
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TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS P'
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE ACTION
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LDSS OF POWER a.
4.16 kv Emergency Bus Undervoltage (loss of Voltaga) 1.
Emergency Bus
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Emergency Bus l
- 2-3E and 2-4E 2/ Bus 1/ Bus 2/ Bus 11 l
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With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 11 -
None except as provided in Specification 3.0.3.
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- 4':1.;tf e 3/4.3 INSTRUMENTATION BASES 3/4.3.1 NEUTRON MONITORING INSTRUMENTATIch The neutron monitoring instrumentation, which was included in the normal Reactor Protectiori System Instrumentation, provides information regarding the shutdown stt?.us of the core and it will be used to monitor the core and to enscre that the core remains subcritical.
"'~ ith the core in its present subcritical configuration, only the source W
range neutron channels read on scale; the intermediate range channels are reading off scale low. The intermediate range channels would only come on h0.,) )
Therefore, the Action statements have been directed towards establishing a scale if the reactor should reach an approximately critical condition.
,{ckr 8 high priority for restoring inoperable source range channels to an OPERABLE status and towards obtaining NRC approval of the plans for restoring in-operable channels to an OPERABLE status if the inoperability cannot be readily remedied.
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