ML19341B353
| ML19341B353 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1980 |
| From: | Ahearne J NRC COMMISSION (OCM) |
| To: | Bevill T HOUSE OF REP., APPROPRIATIONS |
| References | |
| NUDOCS 8101300784 | |
| Download: ML19341B353 (14) | |
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,c UNITED STATES CC' uc5 ION y
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h NUCLEAR REGULATORY COMMISSION CcEETCDUICE
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- E WASHINGTON. D. C. 20555 e,.
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m December 31, 1980 esamuru t
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$Y The Honorable Tom Bevill, Chairman
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cij Subcommittee on Energy and Water Development
=;2 Co=nittee on Appropriations X
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United States House of Representatives 0;
u Washington, D.C.
20515
Dear Mr. Chairman:
The first monthly status report, in response to the directions given in
' House Report 96-1093, was transmitted to you by letter, dated November 21, 1980 and covered the time period from April 17, 1980 to November 15, 1980.
The second monthly status report is enclosed and covers the period from November 15, 1980 to December 15, 1980.
This second report discusses the actions that were taken during the last month for operating reactors and on licensing reviews of new facilities.
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John arne
Enclosure:
NRR Monthly Status Report to Congress cc: The Honorable John T. Myers 810130019L/
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NRR P.3NTHLY STATUS REPORT TO CONGRESS The first NRR monthly status report to Congress, in response to the direction given in House Report 96-1093, was transmitted by letter dated November 21, 1980 and covered the period from April 17, 1980 to November 15, 1980. This is the second monthly report covering. the period between November 15,-
1980 and December 15, 1980. This report provides a brief discussion of the major actions that were taken on operating reactors and on licensing reviews of
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new facilities during that period of time.
Operating Reactors During the reporting period, the major issues on operating reactors receiving staff attention included development of additional requirements for all operating BWR plants to improve the reliability of BWR scram discharge systems, the evaluation of licensee submittals from all operating reactors regarding the environmental qualification of safety-related electrical equipment, and the evaluation of water leakage into the containment at Indian Point, Unit 2 which submerged part of the reactor vessel.
A discussion of these follows.
On June 28, 1980, during a routine shutdown of the Browns Ferry Unit 3 BWR reactor, a manual scram failed to insert all of the control rods. Two additional attempts were made before all rods were inserted.
The failure of a large number of rods to fully insert in the core after the initial scram signal, which had been considered highly unlikely, was attributed to the unexpected response of the scram discharge volume hydraulic system (caused'by the accumu-lation of water in the scram discharge volume prior to scram).
Failure to l
insert in a few minutes all, or nearly all, of the control rods in a BWR after some transients could result in a severe accident.
As a result of this event, I
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a major effort was undertaken by the NRC staff to reanalyze BWR scram discharge volume systems with the objective of identifying design changes that would improve system reliability. The staff's evaluation, " Generic Safety Evaluation i
of BWR Scram Discharge Systems", dated December 1,1980, was issued to the publici for infomation on December 9,1980.
The report identifies certain interim actions that can be taken on some BWR plants to improve scram system reliability.
We are continuing It also provided criteria for long-term design improvements.
to work on this matter to insure that the implementation schedule for the interim modifications reflects the need for prompt action and provides adequate time for detailed design reviews, procurement, installation, and testing.
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The staff is continuing its raview of the infomation submitted by licensees of all operating reactors on the environmental qualification of safety-related electrical equipment, and plans to complete its assessment of the quali-During this fication status of licensee equipment by February 1981.
report period, meetings were held with licensees to clarify the requirements l
23, 1980.
for equipment qualification defined by a Commission Order, dated May Licensees have identified a number of important issues which are presently being assessed by them and the staff, and may become the subject of public
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Following completion of the staff's assessment, 1
' hearings on some plants.
licensees will be infomed of any necessary actions to meet the requirements of I
In this regard, a related order was issued l
the May 23, 1980 Commission Order.
f by the staff to all licensees on October 24, 1980 requiring that, by June 1982 the subject equipment be qualified to the current criteria, with appropriate documentation, and that, by December 1,1980, a central location be established at each reactor site for all records which document the qualification status of the equipment.
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17, 1980, In the incident at Indian point, Unit 2, which occurred on October gallons of cooling water leaked from piping inside containment and over 100,000 The water leaked from the submerged about one third of the reactor vessel.
service water system (not part of the primary coolant system) which uses the NRR's response to'the. incident included Hudson River as its source of water.
working with the Office of Inspection and Enforcement in preparing the bulletins and enforcement action on this issue, briefing the Commission and the ACRS, and conducting an independent evaluation of the effects of this cold water on the outside of the. heated reactor vessel.
In addition, generic implications of the incident are being considered, such as the adequacy of available means of detecting leakage of water from systems, other than the reactor coolant system, in the containment of other plants.
During the past month, a number of actions have been taken to minimize the effects of the shortage of staff operator licensing examiners which was discussed We have contracted for six examiners through the Oak Ridge in the.last report.
We are continuing our recruitment program and have National Laboratory.
In addition, we have established extended offers to two qualified applicants.
an operator licensing section (to include five examiners and a section leader) in the Region III office, which should improve efficiency and enhance our recruitment efforts in this area.
Licensing - Casework During the past month, the emphasis on licensing activities continued to be with Since the last report, one plant (LaSalle, Unit 1) near tenn OL applications.
has been removed from the impacted plant list (plants for which licensing is
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complete after the expected completion of major items of construction) and two i
The reasons plants (Zimmer and McGuire, Unit 1) have been added to the list.
I for these changes are as follows.
For LaSalle, Unit 1, the applicant recently infomed us that it currently
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Therefore estimates that construction will not be completed until June 1981.
our current projection of April 1981 for completing the licensing effort is no longer impacting the schedule for operating this plant.
In'the case of Zimmer, the staff has detemined that the licensing schedule provided in the last report (Attachment 4 to the report) did not provide sufficient time for the resumption and completion of the hearing process (which lengthens the schedule by three months and places Zimmer in the impacted plant To minimize the now recognized impact on the estimated o'perational category).
readiness date, the schedule for issuing the SER supplement'Will be accelerated by one month to June 1981 reulting in a licensing effort completion date of January 1982 (a net impact of two months).
A Caseload Forecast Panel visit l
within the next few months will establish a more current staff estimate of c5mpletion of construction for Zimmer.
McGuire, Unit 1 is now an impacted plant because the Licensing Board has reopened the hearing, by Order dated November 25, 1980, to consider the issue of hydrogen control in this plant. This plant has an ice condenser containment ' design similar to Sequoyah.
The Board Order indicated that litigation
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of the hydrogen control issue would not affect its approval for fuel loading and zero power testing. However, issuance of a decision on a license (greater than 1
. zero power) cannot be reached until the hearing, tentatively scheduled to commence during the first quarter of 1981, is completed. The impact of this action on issuing a full power license is estimated to be about five months.
With regard to the other impacted plants (Diablo Canyon, Units 1 and 2, San For the Diablo Onofre, Unit 2 and Sumer, Unit 1) the status is as follows.
Canyon units, contentions on fuel loading and low power testing issues.were filed;by all parties on December 3,1980. The nature of those contentions are currently being reviewed to ascertain, among other things, how they will affect the length of hearings, the need for further appeals, and the detemination by the Licensing Board concerning whether there is an advantage in separating low.
Estimates which reflect power and full; power issues for hearing and decision.
our current assessment of the contentions indicate that an ASLB decision re-garding e low power license for Unit 1 would slip to June 1981, followed by a review by the Appeal Board and Commission, which leads to a September 1981 projection for licensing. The impact of this action is estimated to be eight months. An ASLB decision regarding a full power license for both Unit 1 and l
Unit 2 is projected for September 1981 with licenses is' sued in December 1981.
This additional delay corresponds to an overall delay of eleven months and six months for Unit 1 and 2 respectively.
There is no change in the target dates for San Onofre, Unit 2.
The geologic and seismic review and input to the Safety Evaluation Report (SER) have been completed by the staff,-based on completed studies by the U.S. Geological Survey and other consultants.. The SER is still scheduled to be completed in February 1981 with the start of hearing expected to be in July 1981.
. 3 For~ Summer, Unit 1 SER issuance'is.ow projected for January 1981.(one month delay) due to the seismic review and a significant number of other technical m'atters (e.g., fracture toughness data' for.contaimient pressure. boundary com-ponents, stability-of-subsurface-materials and foundations of the service water pumphouse and intake structure, and emergen:y planning) that' require resolution.
If the SER is issued in January 1981, the current target date of October 1981 foi completing the licensing effort can still be met.
However.
in crder to issue a complete SER in January 1981, resolution of many of the open issues.is required.
In' addition, the staff is awaiting a final report
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from the U.S. Geological Survey regarding the potential impact of the
.. Charleston, South Carolina earthquake on the seismicity of the site and lhe region.
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An' updated summary for the impacted plants is presented in Attachment 1.
The status on plants which have been issued a low power license and for which a full power license is pending (Salem, Unit 2 and Farley, Onit 2) is as
.foll ows.
'Jith respect iio Salem, Unit 2,'. issuance of a full power license will be delayed due to the status of developmen't of State and local emergency plans.
The l
licensee has'.netif.ied us that there will be a delay of about a month in the development.of the New Jersey plans and their submission to FEMA, with a corresponding delay in the conduct of an emergen:y exercise which had besn terceted previously for January 1981.
A full power license cannot be issued until the exercise is conducted and fGC receives an assessment cf the exercise nsa
- A full power license for Farley, Und 2 is now projected for March 1981 (a delay The basic reason for this change is that the licensee would not oftwomonths) be ready for a full power license b'efore then since it now projects a fuel load 2
date during February 1981.
t 15, 1980) provides the current target milestone dates (as of December for all pending OL applications and for those plants under construction whose Target dates projected construction completion dates are prior to January 1986.
which have been changed since the last report are identified with an underline.
As noted in the previous report, the staff's proposed manner and extent to which the TMI Action Plan should be applied to pending CP applications (NOREG-To date, a number of 0718) was issued for public comment in October 1983.
comments have been received, mostly from the applicants and their contractors.
Staff resources have been committed to an expeditied assessment of these Following a Commission comments and to revise the NUREG-0718 document this month.
decision on the revised document, further case-specific action to the include TMI-related requirements can be undertaken for the pend'ing CP applications.
Attachments:
December Report - Updated Summary for Impacted OL Plants Target Dates of Licensing Steps for Plants Seeking Operating Licenses 1.
2.
in the Next Five Years
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ATTACfMENT 1 4
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DECEMBER REPORT UPDATED SUMIMRY l-Oa IMPKCTED OL PLANTS _
DECEMBER REPORT _
NOVEMBER REPORT.
Licensing Delay (Mos.)_
Construction Effort Complete Complete **
Licensing Delay (Mos.)_
NO CllANGE Construction Complete **__ Effort Complete NO CllANGE NO CilANGE g
2 8
10/81 9/81 (LP) 8/81 NO CilANGE 12/81 (FP) 11 amer 1 4
5/81-(LP) ablo Canyon 1 1/81 9/81 (FP) 110 tilANGE
'8 NO CilANGE NO CllANGE 10 0
5/82 4/81 B On:trs 2 7/81 6/81 4
6 4/81 12/81*
(FP) 12/80 NO CilANGE h
iSalle 1 3
2 9/81* (FP) 1/82 lablo Canyon 2*
6/81 NO CilANGE 0
1 11/81 2/81 (Zero Power) 11/81 1/81 6/81 (FP) 5 immer 0
12/80(LP) 12/80 3
cGuire 1 3/81 (FP) full power Itcense for Unit 2 CThe licensee has elected to get only a CStaff Estimate LP o Low Power License FP = Full Power License
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