ML19323D620
| ML19323D620 | |
| Person / Time | |
|---|---|
| Issue date: | 04/30/1980 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-800425, NUDOCS 8005220034 | |
| Download: ML19323D620 (44) | |
Text
-
O~~f ppk April 30,1980 For:
The Commis.,ioners From:
T. A. Rehm, Assistent for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 25, 1980 i
A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Standards Development C
i Nuclear Material Safety and Safeguards D
l l
Inspection and Enforcement E
Nuclear Regulatory Research F
Executive Legal Director G*
International Programs H
j State Programs I*
Management and Program Analysis J
Controller K
Analysis and Evaluation of Operational Data L
Items Approved by the Comission M**
l Calendar of Speaking Engagements N
Status of Nuclear Power Reactors 0
&/. A.
e, stant for Operations Office of Executive Director for
- No input this week.
Operations
- Deleted from Commissioners and PDR copy.
Contact:
T. A. Rehm 27781 8005220030
e
/
Summary of Weekly Information Report Week Ending April 25, 1980 H_ ope Creek 1 & 2 Public Service Electric and Gas Company is announcing an overall reduction in construction expenditures over the next 5 years, which will result in the delay of Hope Creek Units 1 and 2.
Robinson 2 The reactor w., shutdown last week after a 0.5 gpm steam generator tube leak was detecter's An inspection of the "B" steam generator tubes disclosed that 79 tubes rrquired plugging.
A meeting was scheduled for April 25 to discuss the inspe, tion.
Resoi:. tory Protection Problem at TMI
'(fol kw-up on last week's report)
GP. decided to postpone the TMI containment entry originally scheduled for Apr. 24, until the respirators to be used for re-entry have been certified by NIOSH. NIOSH expects to complete testing of the equipment in two weeks.
Convention on the Physical Protection of Nuclear Material An analysis of the international " Convention on the Physical Protection of Nuclear Material" is being made to determine if any amendments to NRC regulations are necessary to support the Convention.
FY 1981 Budget In response to the Hart Subcommittee Staff, the staff prepared a proposed 5%
reduction to the budget request.
AE0D The AE0D organization and program were presented for the first time to the ACRS LER Subcommit;ee. The presentations focused on the coordination of NRC operational data activities, and the scope ano status of individual office activities.
.a
/
i 0FFICE OF ADMINISTRATION l
Week Ending April 25, 1980 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Received 304 21 Granted 199 5
Denied 50 10 Pending 55 6
ACTIONS THIS WEEK Received (An individual requesting Requests information on him in the Office of the information about himself)
Inspector and Auditor and information on any charges (80-221) made against him and his personnel file.
Charles Varon Requests information on the Abalone Alliance.
(80-222)
(An individual requesting Requests informatien regarding his Reactor Operator information about himself)
License exam results.
(80-223)
(An individual requesting Requests information regarding his Reactor Operator information about himself)
License exam results.
(80-224)
R. L. Fagan, Requests the awarded contract and non-proprietary The Stanwick Corporation sections of the cost and technical proposals in (80-225) response to contract solicitation NRC-04-79-209.
Daniel Metlay, Requests a copy of 47 listed documents dealing with l Indiana University the NRC's decision on the mixed oxide fuel rule-i (80-226) making hearing on GESMO.
Matthew Gillen, Requests a copy of all licente related inspections Amalgamated Clothing performed at Ethicon, Incorporated.
and Textile Workers Union
)
(80-227)
CONTACT:
J. M. Felton 492-7211 l
ENCLOSURE A
.c P
2 Received, Cont'd T. A. Faircloth, Requests a copy of the 1978 Annual Report to Congresa Roosevelt University on the Administration of the FOIA and a copy of (80-228)
NRC's regulations implementing the F0IA.
Aram Schefrin, Requests the names and addresses of former AEC Attorney-At-Law personnel from 1958-1972 who were involved with the (80-229) use of By-Product Radioactive Materials by the Rhode Island Hospital.
Barry Katz, APPEAL TO THE EDO for documents detailing routes and The Press alternate routes through New York State and (80-A-13-80-149)
Pennsylvania for the shipment by truck of spent fuel from Chalk River, Canada to South Carolina.
Granted Peter L. Gustafson, In response to a request for information regarding Attorney-At-Law inspections at Velsicol Chemical COTporation in (80-79)
St. Louis, MI and Velsicol Chemical Rare Earth Burial ite in Gratiot County, MI, mada available this armation.
Lindsay Audin, In response to a request for seven categories of Safe Energy Coalition documents regarding spent fuel pools at Indian Point of New York State Units 1 and 2, made available 15 documents.
(80-143)
John Cutro In response to a request for three categories of (80-172) information regarding NL Industries Colonie Plant, Colonie, NY and the Knolls Atomic Power Laboratories N1skayuna and West Milton, NY, made available four documents.
(An individual requesting In response to a request for any information information about himself) pertaining to himself and another person regarding (80-176) anti-nuclear activities, informed him that the NRC does not maintain files on persons or organizations relating to anti-nuclear activities.
F. A. Alkisswani In response to a request for a copy of NUREG-0627 ES (80-187) and NUREG-0627 titled: "A Safeguards Case Study of the Nuclear Materials and Equipment Corporation Uranium Processing Plant, Apollo, Pennsylvania,"
made available a copy of this report.
I ENCLOSURE A
3 1
Granted, Cont'd Ellyn R. Weiss, In response to a request for a copy of the Review an9 Sheldon, Harmon Evaluation of the B&W Steam Suppl,' System (a Report
& Weiss to the ACRS by a Task Force staff and fellows),
(80-190) made available a copy of this document.
(NRC employee)
Informed the requester the NRC has no information (80-192) pertaining to him in the Office of the Inspector and Auditor or information on any charges made against him.
(An individual requesting In response to a request for all documents and files information about himself) indexed or maintained under his name, informed the (80-193) requester the NRC has no information pertaining to him in its personnel, security or radiation exposure records.
T. Abramson In response to a request for documents between the (80-206)
NRC and the Power Authority of NY regarding design changes or additional equipment that were made when that authority became the licensee for Indian Point 3 and correspondence between the NRC and the Consolidated Edison Company of NY regarding changes in equipment or design as requested by the Power Authority of NY prior to its purchase of Indian Point 3, made available one document.
John E. McKeever, In response to a request for a copy of 25 listed Attorney-At-Law documents, made available the requested information.
(80-210)
Karl Grossman, In response to a request for a copy of NRC translatig Island Closeup News 520: "Radioecological Assessment of the Wyhl Nuclear Service Power Plant", made available a copy of this do::umento (80-215)
(Individuals' requesting Made available information on their Reactor Operator information about themselves)
License exam results.
(80-223 & 80-224)
Matthew Gillen, In response to a request for all license related Amalgamated Clothing inspections performed at Ethicon,-Incorporated,-
and Textile Workers Union made available 23 documents.
(80-227) i ENCLOSURE A
.e 4
Denied Roger Runningen, In response to a request for a copy of NRC's report Small Newspapers on its investigation of alleged security breaches (80-171) at Commonwealth Edison's nuclear power plant at Cordova, Illinois, denied this report in its entirety, the release of which would interfere with an enforcement proceeding and could deprive a person of the right to a fair trial or an impartial adjudication.
Thomas B. Cochran, In response to a request for a copy of the conflict Natural Resources of interest statements submitted by the members of Defense Council, Inc.
the Advisory Committee on Reactor Safeguards, (80-191) informed the requester two members' statements have been placed in the PDR.
An exemption was granted for the remaining 12 members of the ACRS, stating that they need not disclose their statements for 1979 but would be required to make public the reports submitted in 1980.
Christopher H. Buckley, In response to an appeal for documents concerning the Attorney-At-Law Philippine Power Reactor, the Commission granted (79-A-23-79-314) eight documents, denied portions of two documents an9 denied one document in its entirety.
Edward W. Osann, THE ED0 CONTINUED TO DENY ON APPEAL one document Attorney-At-Law relating to the Conrnission's purported finding which (80-A-8-79-527 )
is characterized in the Notice of Opportunity for Hearing on Construction Permit Extension dated November 26, 1979 in Docket No. 50-367.
This draft document contains preliminary advice, opinions and recommendations and does not reflect final agency policy and the release of this document would adversely affect the agency's deliberative process.
ENCLOSURE A
o o
DIVISION OF CONTRACTS Week Ending April 25, 1980 PROPOSALS UNDER EVALUATION 1.
RFP RS-NMS-80-024 Title - Development of an Advanced Material Accounting System Simulation Model Description - Develop a model which will be used by NRC to evaluate current material accounting practices at licensed nuclear fuel cycle facilities and which will serve as an input i.- studying advance data analysis techniques.
Period of Performance - One year Sponsor - Office of Nuclear Material Safety and Safeguards Status - Best and Finals received April 16, 1980 and forwarded to program office 2.
RFP RS-01E-80-253 (Formerly RS-0IE-79-263)
Title - Development of an Automated Vendor Selection System Description - Development of a system to collect and categorize nuclear component vendor-related data and select vendors for inspection, based upon safety significance, inspection history, and other weighted criteria.
Period of Performance - Thirteen months Sponsor - Office of Inspection and Enforcement Status - Competitive range established April 21, 1980.
CONTRACT AWARDS 1.
NRC-10-80-661 Title - NRC Issuances and Indexes Description - Prepare camera-ready copy of monthly NRC issuances (NRCI) and quarterly and semiannual indexes to the NRCI's.
Period of Performance - One year with one year option Sponsor - Office of Administration Status - Fixed Price Requirements Type contract with a ceiling of $73,364 awarded to Data Composition Services, Inc., on April 21, 1980.
2.
NRC-10-80-382 j
Title - Evaluation of Cost / Benefits of Policy for Placement of Documents in PDR Description - Determine most effective approach for assessing the quantitative and qualitative aspects relating to placement of documents in PDR.
Perform analysis of proposed policies and procedures.
i Period of Performance - Ten weeks Sponsor - Office of Administration Status - Pursuant to the NRC's 8(a) program, a Cost-Plus-Fixed-Fee contract in the amount of $38,121 was awarded to the Small Business Administration who subcontracted the effort to Norman Hodges and Associates, an eligible 8(2) concern.
j i
ENCLOSURE A
.e 2
CONTRACTS CLOSED OUT (All administrative action completed c.nd final payment made)
Contract No.
Contractor Close-Out bate AT(49-24)-0082 R. W. Beck & Associates 3/17/80 ADMINISTRATIVE MATTERS 1.
Contract No. NRC-04-79-210 with the National Academy of Public Administration for project entitled " Nuclear Reactor Crisis Management - Alternatives for Government Action." Sponsor: TMI Special Inquiry Group, funded by RES.
As previously reported in the Weekly Information Report of February 29, 1980, the contractor has incurred costs in excess of the amount set forth in the contract.
The work has been completed and accepted.
By letter dated March 26, 1980, the contractor has provided DC with a detailed break-down of actual costs incurred in performance of the contract.
Thc letter cites Government-caused delay and increased report requirements as the cause for the overrun situation.
The NRC Project Officer has confirmed these allegations and advised that the increase requested was reasonable for the additional work performed.
The contractor had requested an increase of $14,440.52 which included additional fee.
However, since the increased work was not outside the original scope of the contract, DC negotiated an increase of $13,623.04 which represents the overrun costs exclusive of fee.
2.
A public bid opening was held on March 25, 1980, for IFB RS-ADM-80-661 entitled "NRC Issuances and Indexes." While reviewing the bids received the Bid Officer discovered a mistake in the apparent low bid from Data-Midwest Services.
Data-Midwest was notified as to the mistake both verbally and in writing.
By letter dated April 4, 1980, Data-Midwest requested permission to withdraw its bid.
By letter dated April 17, 1980, the C0 granted permission for pata-Midwest to,lthdraw the bid since there was clear and convincing evidence as to the existence of the mis-take as required by FPR Subpart 1-2.406-3(a)l.
ENCLOSURE A
DIVISION OF SECURITY Week Ending April 25, 1980 Babcock & Wilcox On April 21 and 22,1980, two employees of the Information Security Branch, division of Security, visited the Security Manager of Babcock & Wilcox (B&W) at Lynchburg, VA. The purpose of the visit was to discuss the "NRC Classi-fication Guide for Safeguards Information" and the information at B&W which is affected by the guide.
1 o
a ENCLOSURE A-
0FFICE OF NUCLEAR REACTOR REGULATION WEEKLY ITEMS OF INTEREST (Week Ending April 25, 1980)
Hope Creek 1 and 2 Today by news release Public Service Electric and Gas Company is announcing an overall reduction in construction expenditures over the next 5 years.
Included in this overall reduction will be expenditures on construction of the Hope Creek Generating Station, Units 1 and 2.
This will result in the following delays in construction completion:
Unit 1 from 12/84 to 12/85 Unit 2 from 12/86 to 12/88 No immediate impact on staff resources is anticipated since the Hope Creek OL application has not been tendered.
Davis-Besse, Unit No. 1 (DB-1)
On April 17, 1980, the plant staff at DB-1 informed the resident inspector of non-conservative assumptions used in the calculation of offsite dose consequences of a steam generator tube rupture accident. These non-conservative assumptions are a result of the current requirement to trip reactor coolant pumps (RCPs) when a Safety Feature Actuation System signal occurs on low reactor coolant system pressure. The tripping of RCPs leads to two events not previously assumed in the Final Safety Analysis Report analysis:
(1) pressurizer spray is lost, and (2) auxiliary feedwater (AFW) pumps automatically actuate.
Loss of pressurizer spray may result in reactor coolant system pressure variations different from that assumed.
The auto-matic actuation of AFW pumps leads to a new effluent path since the pumps are steam turbine ~ driven, and the turbine exhaust is directed to the atmosphere.
Region III is following up the licensee's evaluation of whether or not the offsite dose consequences of this accident at DB-1 are potentially larger than those previously calculated.
4 ENCLOSURE B
.. t Robinson 2 i
The reactor was shutdown last week after a 0.5 gpm steam generator tube leak was detected.
Since then all tubes in the "B" steam generator have been inspected; the inspection disclosed that 79 tubes required plugging.
CP&L is now re-inspecting the other two steam generators; Steam Generators c
A and C had been repaired and partially inspected in March after another tube leak. A meeting is scheduled for Friday, April 25, 1980 to discuss the results of both inspections.
Brunswick On April 22, 1980 two workers were hurt while welding / cutting in the Radwaste Building.
A plastic sleeve that was installed on the welding leads to prevent contamination exploded.
The workers were taken to the hospital by ambulance.
One was repor+ed to have a concussion and the other suffered two possible broken bones in the neck.
No equipment was danaged.
4 1
1 t
ENCLOSURE B.
HRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of:
April 19 - 25,1980 Plant Status Core Cooling Mode: Cyclic natural circulation in the "A" reactor coolant system (RCS) loop v'ia the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient.
s Available Core Cooling Modes:
0TSG "B" to the main condenser; long term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode:
Makeup system in conjunction with letdown flow (Emergency use only due to RCP seal injection isolated due to suspected leaks in system).
Major Parameters (As of 0400, April 25,1980) (approximate values)
Average Incore Thermocouples: 143 F Maximum Incore Thermocouple:
183'F RCS Loop Temperatures:
A B
Hot Leg 146 F 150*F Cold Leg (1) 107 F 81 F (2) 124 F 83 F NOTE:
A loop recovering from flow period (" burp")
RCS Pressure:
200 psig (Heise)
Pressurizer Temperature:
302 F (Saturation Pressure 69 psig)
Reactor Building:
Temperature:
80 F Pressure:
.44 psig (Heise)
Water level: Elevation 290.5 ft. (8.0 ft. from floor) via decay heat system Elevation 290.1 ft, via penetration 401 manometer Environmental & Effluent Information l.
Liquid effluents from TMI-l released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
2.
No liquid effluents were discharged from TMI-2.
3.
Results from EPA monitoring of the environment around the TMI site were:
EPA environmental stations registered background levels for air particulate and water samples.
ENCLOSURE B
2 Gas air sample results (Kr-85) for the ptriod April 15-19, 1980, Observation Center - 38 pCi/m5.Middletown - 19 pCi/m3, and TM were:
Bainbridge - 22 pCi/m3 EPA states that samples collected in the vicinity of TMI in recent months show background levels of Kr-85 to be in the range of 20-40 pCi/m3 cf air.
NOTE:
The Kr-85 results reported in the Weekly Status Report dated April 21, 1980, were reported with improper units; the results of 34 pCi/l and 24 pCi/l should be changed to 34 pCi/m3 and 24 pCi/m3.
For the period April 21-24, 1980, direct radiation (gamma) readings showed no levels above background.
4.
Radwaste shipments off site were as follows:
On Monday, April 21,1960, a Unit 2 reactor coolant sample was sent to the B&W Lynchburg Research Center, Lynchburg, Virginia.
On Thursday, April 24, 1980, a sample of EPICOR II effluent was sent to the Maryland State Department of rNalth.
On Friday, April 25, 1980, an air sample filter was sent to Teledyne Laboratory, Westwood, New Jersey.
5.
EPICOR II processing. status:
(Auxiliary building approximate quantities)
Amount processed this week:
25,000 gallons Amount processed to date:
225,000 gallons Amount to be processed:
220,000 gallons Major Activities (Past and Present) 1.
The reactor coolant system remains at the first plateau (200 psig) in the depressurization plan to 100 psig.
Results of the April 21, 1980, sample indicated total gas at 42.cc/kg (an increase of 31 cc/kg from previous sample results).
The licensee suspects an inleakage into the sample container during shipment since the oxygen and nitrogen concentrations increased in the same proportion that oxygen and nitrogen exist in air.
The hydrogen concentration remained at approximately 12 cc/kg.
The licensee intends to take another sample on April 28, 1980, to verify sample results before proceeding on with the depressurization plan.
Review of this area by the onsite staff is ongoing.
2.
On April 22,1980, at 5:00 p.m., the National Institute of Occupational Safety and Health (NIOSH) notified the NRC of possible modifications in the personnel respiratory protection system which would be used by the licensee for initial containment entry.
The NRC requested NIOSH to perform examinations of this respiratory protection equipment to determine the status of equipment certification.
On April 23, 1980,
'l NIOSH representatives arrived at the TMI site and examined the
$.u ENCLOSURE B
3
,o respiratory equipment in question, and determined that the manufacturer had performed modifications which were not previously tested and certified by HIOSH. On this basis, the Deputy Program Manager notified the licensee that no entry would be made until the breathing equipment can be retested and certified by NIOSH.
NIOSH representatives are currently examining and testing a sample of the licensee's respiratory protection equipment to determine adequacy of these modifications and status of equipment certification by HIOSH.
This test is expected to be completed within the next two weeks. Containment entry is now postponed pending completion
(.f NIOSH testing and certification of these modifications.
3.
GROUND WATER MONITORING PROGRAM STATUS. All eight ground monitoring wells are functional.
Samples were taken from these wells daily from April 11 to April 18, 1980.
Composite, split samples were sent to four laboratories for analysis.
The tritium analysis from the participating laboratories is included in Table 1.
No other radioactive isotopes were identified in the samples.
Based on the consistency of the daily sample results, sampling frequency will be reduced to once per week.
The NR0 had a concurrent sample collected from all wells on April 17, 1980, for independent analyses by the NRC Region I laboratory.
The gamma isotopic analysis performed by the NRC Region I showed no levels above Lower Limits of Detection (LLD).
The NRC Region I analysis confirmed tritium levels in well water between 446 and 985 pCi/1.
These analytical results are consistant with the previously reported licensee's data and continued to show tritium levels above natural background (200-300 pCi/1).
Based on sample trends to date, and the relatively low tritium content in the well water, it was agreed that well water would be pumped directly to the storm drains if sample results were avail-able from water pumped during the previous week.
l The source of the brown color in wells #2, #3, and #8 has not been identified. Test results to date have not identified anything in the water which would prohibit discharge to the river.
The NRC has requested a copy of all brown water test results.
The test results will be forwarded to the PA-Department of Water Resources by the licensee to determine whether the water meets state criteria for discharge to the river.
Seven additional observation wells are being drilled in various locations around the TMI-? reactor building.
It is hoped that the observation wells will help identify the source of the higher tritium levels in wells #2, #3, and #8.
Observation well drilling commenced on April 22, 1980.
Barring weather problems and equipment failure, one observation well should be completed each day.
Five observation wells will be drilled to bedrock.
The two observation wells west of tne reactor building will be drilled 15 feet into the bedrock to detect any potential water migration through the bed-
- rock, i
ENCLOSURE B l
e_h. crrotNcv, uNG s
No croc TABLE I T = daltdyna
-t
.RMC = RMC II Analysis 3
OR = Oak Ridge pCi/ liter TVA = TVA Ditc/lal
- PN2 8
PM3 r IN7
- FN8
- Pond i'
is is is 4/11 Ti 10101110~
~5605590
~
7001 80 ~
~
~
~
10601100 190170'
' ' ' ~
.__.._.0d05~ '
77bi200
-. _<3_50IU.".<'3 0 6._'_0_
<300.0
_ ___RMCs.
. _30_0.0
_.690_i20_0. <.250 _..
8
. _ 0R TVA*
178157 921i 79 2661 58 252 _1 59 ___160_157._._3_0_1.6. 0._4__361 60 885 74 ___17__215. 5.
4 /12.T.*
9201 80 7201100 10201100
<100
.. _ _K.M.C '.
_< 2 5 0. -.. _.810118_0_ _60011_7.0
<250
<2.50. -
<250_-- _ 3_0. 0.i160 -.7_10120.0
<3.0. 0-O R_*.
TVA*
135156 774i 74 358 60 3011 60 3561 61 393i 63 7931 75 123iS4 is 4/13 P' 980 110~
690i 90 790i100 ' 100180"
~~ ~
~
<500.
5802U0 440i190
<30b
~
RMO:
~'
<250 2901160 330 160 810il70
<250 Omi
- TVha 252159 860t 77 4491 63 2641 59 3331 60 6651 67 100 50 BS
<4/14 ?*
t010 100 590 70
~~~
860 100 90280
' ~~
~~~ ~
~ ~ -
' U
._.R.
Ct'.. I. 2.5. _5....
- 8. 4_0i_.l.70__6401160.._< 2 5. 0. __...
..<. 25 6
~<25U~
~5bi160
~
~ ~ ' '
2 6._20. _160 _
.. ORio
.... TV Ai' 10561 81..
4.70i.65 _.293 38 235?S7 4111.60 6171 65 a.
4/15 T's 6101 80 1040!100 5701 90 110180 RMC88 ORas TWa*
. ~.--..
39
.A..f.f. kL.ft.i ?T. MC& &GS.
~
se m
ll:':
n aP O
se v,
C so
- X3 m
30 g
3:
G 6
y The licensee cnnsiders that background tritium activity in thQ river surrounding TMI is 200 - 500 picocuries per liter.
EPA records examined by the f1RC indicate that background tritium in the general area is 200 picocuries per liter.
The next ground water monitoring meeting is scheduled for 10:00 a.m.
on Thursday, May 1, 1980.
Future Evolution ilo firm evolutions are planned other than addressed above under i
Major Activities.
o=,
I l
l ENCLOSURE B
6
.c Meetings H71d with Public Officials and Interested Groups 1.
On April 21, 1980, J. Collins met with representatives of PA-DER and DOE to discuss the status of the Community Monitoring Program.
2.
On April 23, 1980, H. Denton, J. Collins, T. Elsasser, and E. Bretthauer, EPA, attended a meeting at 9:30 a.m. in Camp Hill with the Presidents of the Medical Society in the 5th Consular District.
3.
On April 23, 1980, J. Collins, T. Elsasser and E. Bretthauer, EPA, conducted a briefing at 7:00 p.m. in Mount Joy for elected officials from the following communities:
Conewago ivwnship (East Shora),
Conoy Township, East Donegal Township, Elizabethtown, Mount Joy, Mount Joy Township, West Donegal Township, the City of Lancaster, and Lancaster County.
A total of 22 officials were invited; 17 attended.
4.
On April 24,1980, at 9:00 a.m., H. Denton, J. Collins, T. Elsasser and E. B'atthauer, EPA, met with the Chamber of Commerce heads from:
Harrisburg, _ancaster, Lebanon, York and the West Shore.
Approximately 100 people attended.
5.
On April 24, 1980, H. Denton, T. Elsasser and E. Bretthauer, EPA, met with the Mayor of York.
6.
On April 24, 1980, H. Denton, B. Snyder, T. Elsasser and E. Brettauer, EPA, met with various civic leaders and interested citizens from the Lebanon area.
Approximately 120 people attended.
7.
On April 24,1980, at 7:00 p.m., J. Collins conducted a briefing in Hummelstown for officiala from the following communities:
Harrisburg, Hershey, Hummelstown, Lower Paxton Township, Paxtang, Penbrook, South Hanover Township, and South Londonderry Township.
A total of 22 officials were invited; 2 attended.
8.
On April 26, 1980, J. Collins met with Congressman Ertel and representatives from Met-Ed to discuss the issue of venting the TMI-2 reactor building.
Future Meetings 1.
On April 28, 1980, J. Collins will appear on a talk program on WLBR radio, Lebanon to answer questions from listeners about the cleanup operations.
2.
On April 28,1980, at 6:30 p.m.
J. Collins will speak to the Elizabethtown Kiwanis Club on the cleanup operations at TMI.
3.
On April 28,1980, at 7:30 p.m., J. Collins, T. Elsasser and E. Bretthauer, EPA, will meet with representatives from area school boards at the Middletown High School.
4.
On April 30,1980, at 9:00 a.m., J. Callins, T. Elsasser and E. Bretthauer, EPA, will meet in Middletown with religious leaders from the Harrisburg area.
ENCLOSURE B
.o s
7 5.
On April 30,1980, at 1:30 p.m., J. Collins, T. Elsasser and an EPA representative will meet with the York County Commissioner in York.
6.
On April 30,1980, at 4:20 p.m., J. Collins and T. Elsasser will meet with teachers from Northeastern Senior High School in Manchester.
7.
On May 1,1980, J. Collins will appear on a talk program on WAHT radio, Lebanon, called "Two Way Radio" to answer questions from listeners concerning the cleanup operations.
8.
On May 2,1980, at 9:30 a.m., J. Collins and T. Elsasser will meet with tne Mayor of York.
4 9.
On May 2,1980, J. Collins and B. Snyder will brief the ACRS on the status of the cleanup operations at TMI and the status of the Programmatic Environmental Impact Statement.
9 10.
On May 5,1980, J. Collins will address the 9th grade Civic Classes at East Junior High School, Harrisburg.
11.
On May 5,1980, at 7:00 p.m., J. Collins, T. Elsasser and E. Bretthauer, EPA, will conduct a briefing in Manchester for officials from the following communities:
Conewago Township (West Shore), Dover Township, East Manch. ester Township, Hellam Township, Manchester, Manchester Township, Mount Wolf, Springettsburg, Warrington Township, and York Haven.
12.
On May 8,1980, J. Collins will address the Lower Swatara Lions Club at 6:30 p.m. at the Skyways Inn.
I ENCLOSURE B
- 4 i
0FFICE OF STANDARDS DEVELOPMENT IMPORTANT EVENTS FOR THE WEEK ENDING APRIL 25, 1980 1.
Respiratory Protection Problem at TMI: A preliminary report on this problem was provided last week. On April 22 the agency that certifies respirators (NIOSH) informed a member of the SD staff that the manufacturer of the respirators to be used for the TMI containment re-entry, scheduled for April 24, 1980, might have made modifications to the equipment that were not in accordance with the NIOSH certification.
SD telephoned this information to the NP.C support group at TMI and arranged a meeting that was held on April 23, 1980, among NRC, NIOSH, and the licensee (GPU) at TMI to determine whether the equipment could be used.
Upon examination, the equipment was determined to have been modified by the manufacturer.
GPU representatives asserted that the manufacturer had assured them that the modified equipment was tested and certified.
The manufacturer's representative, who was present, did not deny that assertion and admitted that some modifications had been made without application to NIOSH for extension of certification.
GPU decid9d to postpone the containment entry until this problem is resolved. The equipment may be returned to tested-and-certified status by replacement of ori'ginal-type parts, or the manufacturer may apply to NIOSH for an extension of certification to the equipment as modified.
The latter course is being attempted.
NIOSH has borrowed four of the modified units from TMI for immediate testing.
NIOSH estimates about two weeks for completion of the tests. Should the modified equipment fail the tests for certification, the manufacturer believes that restoration of the equipment to original certified status could be accomplished within a day or two.
The licensee would still prefer to use this equipment, if possible, both for the advantage of increased working time in the containment building and because the substitution of different equipment would require retraining of the re-entry teams and modifications of the approved re-entry procedures.
[
Contact:
J. L. Caplin (443-5970)]
I 9
4 ENCLOSURE C
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=A 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending April 25, 1980 National Radioactive Waste Management Program In order to enable NRC to adequately respond to input requested for the President's National Radioactive Waste Management Program and for budget purposes, Fuel Cycle staff requested DOE to provide its projected license application schedules for its away-from-reactor (AFR) spent fuel storage program. The tentative schedules assume:
(1) authorization in FY 1981 of funding, (2) completion in April 1981 of an AFR facility acquisition EIS, (3) successful negotiations for purchase of existing facilities, (4) that design and lit :nse application efforts meet their schedules, and (5) completion in 1982 of an EIS for new facilities at existing and/or new sites.
Given these assumptions, license application submittal dates are:
1.
Morris license transfer.and reracking - July 1981 2.
Barnwell (reracked) - October 1981 3.
West Valley license transfer and reracking - October 1981 4.
New 5000 MTU facility - January 1984 Meeting with UK Nuclear Installations Inspectorate On April 21, representatives of NMSS met with members of the UK Nuclear Installations Inspectorate (NII) to discuss nuclear criticality safety and licensing of fuel processing plants.
The nuclear criticality safety policy in the UK appears to be similar to that in the U.S.
The depth of safety expertise in the UK licensee organizations permits more of in administrative review by the regulatory agency and a clearer understanding that the licensee has full responsibility. The NII has a policy of not getting involved in detailed review of nuclear criticality safety analyses, but does require submittal of the analysis documents and records of the licensee safety committee meetings.
ENCLOSURE D
3 0
- e Items of Interest 2
Convention on the Physical ' Protection of' Nuclear Material An analysis of the international " Convention on the Physical Protection of Nuclear Material" is being made to determine if any amendments to NRC regulations are necessary to support the Convention. This analysis could result in forwarding proposed rules for Commission action.
Review of Swedish KBS-II Plan for Disposal of Spent Nuclear Fuel by National Academy of Sciences The National Research Council iaf the NAS recently completed a review of the Swedish KBS-II Plan and issued a report on their findings.
The NAS has concluded, among other things, that:
(1) the effectiveness of a thick-walled copper canister surroun.ded by bentonite clay to contain radionuclides in spent fuel rods for hundreds of thousands of years has been adequately demonstrated for conditions that exist in a deep granite environment and (2) the final demonstration of the adequacy of a site for a deep geologic repository can be made only by sinking a shaft and driving exploratory tunnels.
This confirms the feasibility of constructing packages which will contain high-level radioactive wastes for thousands of years and supports the staff's contention that in-situ testing is essential to proper characteriza-tion of a potential repository site.
feeting with New York State Authorities Regarding Shipments of Spent Fuel SG staff met with members of various organizations representing the New York state government concerning shipments of spent fuel through the state.
Discussions centered around NRC's protection requirements for the shipments and the route approval process.
New York state representatives were primarily interested in how the state could interact with the NRC during this process, and the extent to which specific information concerning the approved routes could be transmitted to state agencies.
New York has agreed to provide the NRC with a written request containing exactly the information they need and the agencies to whom the information would be transmitted.
ENCLOSURE D
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending April 25, 1980 1.
The following Notification of Significant Enforcement Acti.on was dispatched:
a.
EN-80-14 Consumers Power Company (Palisades) - Confirmatory Order for Licensee's Response to IE Bulletin 79 On April 23, 1980, a Confirmatory Order was issued to Consumers Power Company to formalize the commitment from the licensee to respond to IE Bulletin 79-27.
The licensee has committed to complete the required review prior to resuming operations on or about May 1, 1980.
IE Bulletin 79-27 dealt with the loss of non-Class-1-E instrumentation and control power system bus during operation.
2.
Preliminary Notifications relating to the following actions were dispatched
~during the past week:
a.
PNO-I-80-60 Peach Bottom Units 2 & 3 - Valve Isolation Room Overpressure Transient b.
PNO-I-80-61 Nine Mile Point Unit 1 - Turbine Building Fire c.
PNO-I-80-62 Beaver Valley Unit 1 - Unplanned Release of Extended Duration d.
PNO-I-80-63 Maine Yankee - Contract Guard Employee Injured on Firing Range e.
PNO-II-80-64 General Electric Company, Wilmington, NC - Evacuation of Fuel Manufacturing Building - False Criticality Alarm f.
PNO-II-80-65 Pilgrim Nuclear Power Station - Allegations Regarding Burial of Spent Fuel g.
PNO-II-80-66 Brunswick Units 1 & 2 - Contractor Employee Injury h.
PNO-II-80-67 & -67A Surry Units 1 & 2 - High Radiation Levels on Surface of Radwaste Shipment Vehicle i.
PN0-II-80-68 Bellefonte Unit 1 - Work Stoppage - INRYC0 Tendon Installation j.
PNO-II-80-69 Wittaker Memorial Hospital, Newport News, Virginia -
Notice of Film Badge Overexposure k.
PN0-II-80-70 Hartsville Unit A Iron Worker Injured 1..
PNO-III-80-72 Clinton Units 1 & 2 - Act of Vandalism in Radwaste Area m.
PNO-III-80-73 Davis-Besse Unit 1 - Loss of Instrument Power / Loss of Decay Heat Cooling / Refueling Mode ENCLOSURE E
2 n.
PN0-III-80-74 Zimmer - Allegations of Defective Welds o.
PNO-III-80-75 Quad Cities Unit 2 - Return to Operation Following an.
Extended Outage p.
PN0-IV-80-17A South Texas Unit 2 - Settlement of MEAB #2 q.
PNO-V-80-29 San Onofre Unit 1 - Minor Contaminated Personnel Injury r.
PNO-V-80-30 San Onofre Unit 1 - Loss of Power at San Onofre Unit I s.
PNO-V-80-31 San Onofre Unit 1 - Request by Governor of California for Information Concerning a Contamination Incident t.
PNO-TMI-80-24 Three Mile Island Unit 2 - Gaseous Release from EPICOR II u.
PNO-TMI-80-25 Three Mile Island Units 1 & 2 - Decoupled Trailer-Tractor Hauling Radwaste, Middletown, PA Intersection v.
PNO-TMI-80-26 Three Mile Island Units 1 & 2 - Fire at TMI Observation Center w.
PN0-TMI-80-27 Three Mile Island Unit 2 - TMI-2 Airlock Purge in Preparation for Reactor Building Entry x.
PN0-TMI-80-28 Three Mile Island Unit 2 - Postponement of Initial Unit 2 Reactor Building Entry y.
PNS-I-80-06 Three Mile Island Unit 1 - Reported Possible Unauthorized Entry to Owner Controlled Area z.
PNS-II-80-09 Yellow Creek - Bomb Threat aa.
PNS-II-80-10 Sequoyah. Units 1 & 2 - Bomb Threat bb.
PNS-IV-80-08 Wolf Creek Unit 1 - Suspected Sabotage of Electrical Cables cc.
PNS-IV-80-09 River Bend Units 1 & 2 - Bomb Threat 3.
The following IE Information Notice was issued:
a.
IE Information Notice 80-15, " Axial (Longitudinal) Oriented Cracking in Piping," was issued on April 21, 1980 to all light water power reactor facilities with an operating license or construction permit.
ENCLOSURE E
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0FFICE OF NUCLEAR REGULATORY RESEARCH Important Itens - Week Ending April 25, 1980
~'
The NRC-DOE Joint Coordination Group for Improved Reactor Safety met on April 16.1980.
Attending for NRC were Budnitz, Bernero, DiSalvo and Beckwith; for DOE were Matlock, Pressesky, Norin and Matovich.
Recent administrative an.d technical developments related to each agency's research on improving reactor safety were reviewed.
An interagency programmatic agreement was signed in December 1979 chartering the Joint Coordination Group and outlining a mechanism whereby DOE would undertake and conduct certain work directly responsive to NRC's program.
Based upon the results of NRC's research to date, guidance was provided in a letter to DOE on February 6.1980 outlining work scopes and desired end products in specific research areas. These included add-on decay heat removal system, vented filtered containment system, hydrogen control techniques, improvements in operator-machine interface and advanced seismic designs.
l All of DOE's funds in FY 1980 'were committed prior to receiving the NRC guidance.
DOE requested supplenental funds in FY 1980 to conduct the work recommended by NRC but the Office of Man:gement and Budget denied the reques t.
Efforts to make funds available through internal reprogramming have been unsuccessful because of higher priority needs related to Three Mile Island recovery.
DOE programs responsive to a pair of NRC's unresolved safety issues. Reactor Vessel Katerials Toughness and Containment Emergency Sump Reliability, are scheduled for completion in 1980 and 1981, respectively.
The major conclusions of.ns neeting were as fo:10ws:
1.
The current and propost.
1E program is responsive to NRC's guidance regarding operator-machirs interface.
2.
DOE is most interested in initiating work on alternate decay heat removal systems in FY 1980 but is unable to do so unless efforts to locate additional funds are successful.
DOE intends to include the recommended work on decay beat removal systems in its FY 1981 program.
3.
DOE will look to its Technology Kanagement Center for recommendations on supporting programs on hydrogen control techniques and advanced seismic designs in FY 1981.
Research on filtered vented containment systems is not contemplated at this time despite NRC's recommendation, but DOE will keep abreast of cu rent developments in this area.
4.
The guidance provided by HRC to DDE in February 1980 is still valid and should be used as a basis for planning FY 1982 programs.
Reaffirmation or additional guidance based on new information will be provided as warranted.
ENCLOSURE F
2 SAFER 1.
Report'NUBEG/CR-0987, "The Impact of Decontamination on LWR Radioactive
~
Waste Treatment Syster.s" was issued.
The purpose of the study was to highlight problems of reactor design and decontamination operations which result from the need to decontaminate, particularly addressing the w
capability of.the nomal radwaste systems to handle the wastes generated.
Some of the principal conclusions of the study were:
e Future plant designs should consider decontamination needs, both the reactor design and the radwaste system design No' current LWR except the N-reactor and Dresden I have radwaste systems e
capable of' handling wastes from either dilute or concentrated solution decontamination
)
e Decontamination of the fuel as well as the primary coolant system is a necessary step of radiation levels are to be reduced during periods
)
after returning to power operation.
e New problems in waste solidification and disposal may result from decontamination.
2.
D. E. Solberg of the SAFER Division Staff presented a paper at the ANS National Topical Meeting on Criticality Safety in El Paso, Texas, on April 8.1980.
The topic cf the paper was "NRC Interests and Involvement in Criticality Data Acquisition." The paper was constructed to answer 1
three basic questions:
e What is the process by which NRC determines its research needs and how does criticality research fit into the total research program of NRC?
c What criticality research is currently being funded by NRC. what is the NRC objective in sponsoring the research and where can the results be found?
c 'Jhat are the expectdd future criticality reseaich needs of NRC*/
1
)
l ENCLOSURE F-
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING APRIL 25, 1980 INTERNATIONAL COOPERATION Arrangement " Renewal" The Japanese Nuclear Safety Bureau and the Agency of Natural Resources and Energy, both parties to the original information exchange arrangement signed with NRC on May 30, 1974, have advised IP that they are ready to sign the latest proposed " renewal" arrangement as soon as a signature date can be sent and the Japanese language version prepared. Although the original arrangement had officially expired last May, we had agreed to continue the information exchange while active negotiations on an acceptable " renewal" text were underway.
Activities with the Canadians IP this week, at NRR request, postponed indefinitely the planned Plant Systems team visit to Toronto, announced in the Weekly Activities Report of April 18, 1980.
The team cited implementation of the NRR reorganization plan as the cause.
The Canadians have indicated their willingness to reschedule the discussions whenever we are ready.
IP, meanwhile, continues its coordination of the p.a zed U.S.-Canadian exchance on identified engineering topics, to take place in Toronto on an as yet unspecified day during the week of May 4.
The NRC team participating in this effort would be headed by Vince Noonan.
Finally, we have proposed that an interagency team (composed of NRC, FEMA, and U.S. Embassy personnel) visit Canada May 29-30, 1980 to explore several emergency planning topics, including plans for dealing with a nuclear emergency near our shared borders and lessons learned from and the Mississauca Evacuation. We await Canadian response to this proposal.
Foreign Visitors to NRC On Monday, Mr. J. T. Daniels of the U.K. Safety and Reliability Directorate, met with representatives of RES to discuss the research aspects of the transportation of radioactive materials.
On Monday, Messrs. K. Smith and J. H. Chalmers, Inspectors from the U.K. Nuclear Installations Inspectorate (NII), met with representatives of the Division of Fuel Cycle and Material Safety of NMSS, to discuss criticality matters, including the application of computer codes and calculation techniques, together with related standards of acceptability and confidence limits. Additionally, the visitors described the U.K. licensing and criticality certification procedures.
On Tuesday, Mr. Ingo Volland, Chief of the Energy Section of the Department of Economics of the Berlin Senate (the chief licensing authortiy for all energy production facilities in Berlin, FRG), met with W. Minners of NRR to discuss post-TMI reactor licensing trends in the U.S.
ENCLOSURE H
,o
.c On Tuesday, Mr. Jean Pierre Olivier of the Nuclear Energy Agency (NEA) met with R. B. Minogue of SD, and representatives of RES, NRR, and IP to discuss the forthcoming meeting on siting of the Sub-Committee on Licensing.
On Monday, Tuesday and Wednesday Srs. Hernandez and Silva, Engineers from the Mexican National Nuclear Safety and Safeguards Commission (CNSNS), and Mr. A. Garland, former NRC employee now on assignment with the IAEA in Mexico, met with K. Campe of NRR to discuss turbine missiles.
On Thursday, Inspector Matti Heikkila of the Finnish Institute of Radiation Protection (IRP) met with R. Satterfield and J. Holman of NRR to discuss (1) environmental testing and reliability analysis, and (2) control room emergency operational procedures. Mr. HEikkila also met with J. Johnson and B. Dennig of PAS /RES to discuss numerical probability in licensing.
On Friday, Messrs. Luigi Baldassari and Fabio Moscati of the Ente Nazionale Energia Elettrica (ENEL) of Italy met with J. Holman of OLB/NRR and S. D. Richardson and J. Wiebe of RSSB/SD to discuss the recommended procedures and standards for operating personnel,with specific emphasi; on changes in simulator design and operations, post-TMI.
On Friday, Mr. Kjill Johansson of Studsvik Energiteknik, Dr. Ingmar Tiren of Asea-Atom, and Mr. Lars G. Larsson, Science and Technology Attache of the Royal Swedish Embassy, met with C. N. Kelber and A. Spano of RES and R. Tedesco and T. Speis of NRR to discuss Swedish research programs on vented containments.
o Foreign Reports i
1 i
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- Deleted from PDR copy.
ENCLOSURE H
s t Foreign Reports (Cont'd)
EXP0RT/ IMPORT AND INTERNATIONAL SAFEGUARDS Tokai-Mura Agreement IP is reviewing a DOE request to extend for a period of one year the Tokai-Mura agreement, which provides for the reprocessing of 99. tonnes of U.S. origin fuel.
IP expects to obtain relevant documentation from the Executive Branch and complete its review of this request and forward it to the Commission shortly.
- Deleted from PDR copy.-
ENCLOSURE H
4 Meeting with GA0 Representatives IP attended a meeting on April 24 at NMSS with two representatives from GA0 (Mark McLachlan and John Trembler). The meeting was held at the request of
.GAO to discuss topics associated with U.S. efforts to strengthen IAEA safeguards.
Of particular interest were the U.S. "P0TAS" safeguards technical support program, the status of the US/IAEA Safeguards Agreement and ACDA's " RECOVER Program," which involves an effort to develop a secure communication system for the remote and continued verification of the status of safeguards devices installed at nuclear facilities throughout the world. A summary was also prc/ided in response to a question raised regarding NRC's effort to obtain additional international safeguards information from the Executive Branch, although the information was not relevant to the principal purpose of the meeting. We understand that GAO intends to complete a draft report on its findings regarding U.S. efforts to strengthen IAEA safeguards in July and publish a final report in September. This report, as well as others, will become part of the comprehensive report required under the provisions of the NNPA, which is due to Congress in early 1981.
4 l
EHCLOSURE H
o 1
0FFICE OF MANAGEMENT AND PROGRAM ANALYSIS 7
Items of Interest j
WEEK ENDING APRIL 25, 1980' Hearing Duration Study Sent copies of MPA's statistical analysis of hearing process to Office Directors.
Requested their comments on (1) factors influencing the lengther,ing of the process, (2) which factors are problems and are within tiRC's purview, and (3) methods that might be used to cope i
with the rroblems.
Management Information Distributed March issue of " Operating Unit Status Report" (Grey Book).
i 4
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ENCLOSURE J
0 Office of the Controller Items of Interest Week Ending April 25, 1980 FY 1981 Budget In response to the Hart Subcommittee Staff, the staff prepared a proposed 5%
reduction to the budget request. This was submitted to the Commission in the form of a staff paper.
FY 1982 Budget Formulation The budget schedules contained in Section D of the Budget Call were to be submitted to the Office of Administration on Friday, April 25, 1980.
l Enclosure K
s OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING APRIL 25, 1980 On Tuesday, April 22, AE00, assisted by NRR, IE, RES-PAS, MPA, and other offices briefed the ACRS LER Subcommittee. The presentations focused on the coordination of NRC operational data activities, and the s; ope and status of individual office activities. The AE00 organization and program were presented for the first time to the Subcommittee. The staff views and actions on the ACRS Report on the Review of LERs (NUREG-0572) were also reviewed with the Subcommittee.
Additional future discussions are anticipated which will address more specific topics on operational data assessment.
4 e
i i
ENCLOSURE L
DN s CALENDAR OF SPEAKING ENGAGEMENTS April 29 Dr. Allen Brodsky, SD, will present a talk on Risk vs. Benefit Assessment and participate in a panel on Government Responsibilities for Producing and Distributing Reliable and Pertinent Information before the American Association of Physicists Meeting in Las Vegas, Nev.
May 9 Dr. Allen Brodsky, SD, will present a talk on Occupational Exposure Measurements in Regulatory Guides before the National Bureau of 1
Standards in Gaithersburg, Md.
4 i
I 1
4 e
ENCLOSURE N
STATUS OF NUCLEAR POWER REACTORS UNDER NRC PURVIEW - MAR. 31, 1980 SOURCE: OFFICE OF MANAGEMENT & PROGRAM ANALYSIS Number Capacity
- Of Units (MWe)
"67 - LI C E N S E D TO O P E R ATE................................. 49,000 (Excludes 3 which have operating licenses but are shut down indef-Initely - Three Mile Island 2,'Humboldt Bay, and indian Point 1) 1 LICENSED FOR LOW-POWER TESTING...................... 1,000 87 C O N STR U CTI O N P E R M IT G RANTED....................... 96,000 36 Under Operating License Review..................... 39,000 51 Operating License Not Yet Applied For................ 57,000 (Excludes 3 which have been denied certification by the N.Y. State Siting. Board - Sterling 1 and Jamesport 1 & 2) 11 U ND ER CONSTRUCTION PERMIT REVIEW.................. 14,000 (Excludes 3 which are indefinitely postponed - Montague 1 & 2, and Clinch River; and 2 which have been denied certification by the N.Y. State Siting Board - New Haven 1 & 2) 166 TOTA L.............................................
1 E9,000***
1
' Net Maximum Dependable Capacity for operating units for which it is established; net Design Electrical Rating for all other units.
- The 67 units have accumulated 458 reactor years of operation. An additional 56 reactor years of operation have been accumulated by permanently or indefinitely shut down units.
- Numbers do not add exactly due to rounding.
NOTE:
Only units docketed by NRC are included. Hence, two status categones
(" Ordered" and " Publicly Announced") included in similar charts issued through December 1979 are not used.
I NP1-40 ENCLOSURE 0 l