ML20207B472

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Forwards List of Plants in Shut Down Category & Related Data.Pb Erickson 851112 Paper Describing Decommissioning Process & Applicable Regulations & List of Licensed Power Reactors to Date Also Encl
ML20207B472
Person / Time
Issue date: 08/14/1986
From: Velez C
Office of Nuclear Reactor Regulation
To: Rich Smith
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
Shared Package
ML19303E617 List:
References
FRN-51FR24078, RULE-PR-171 AC30-2-16, NUDOCS 8612010122
Download: ML20207B472 (13)


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AUG 141986 MEMORANDUM FOR: Ronald M. Smith, Staff Attorney Office of General Counsel THRU: Lars Solander, Chief .

Planning and Resource Analysis Branch $ b Planning and Program Analysis Staff Office of Nuclear Reactor Regulation FROM: Carlos A. Velez, Senior Resource Analyst Planning and Resource Analysis Branch Planning and Program Analysis Staff Office of Nuclear Reactor Regulation

SUBJECT:

SHUT DOWN PLANTS This is in reference to our telephone conversation of Tuesday, regarding plants permanently shut down. As we discussed, there is no statutory definition.of what constitutes a plant " licensed but shut down indefinitely."

Several years ago (perhaps seven or more) the people in charge of the preparation of the Summary Information Report, NUREG-0817 (Brown Book),

decided that some plants that had been shut down for a considerable time period, but for which the utility had not formally submitted a decomissioning plan, should be separated from the rest. That gave birth to the " Licensed But Shut Down Indefinitely" category. T_MI ,[ is the only plant presently in that category; the presumption is that G,eneral Public' Utilities intends to clean-up and restore the reactor, and to resume operations.

I have enclosed some materials that I believe you will find of value.

Enclosure 1 is a list.of plants in the shut down category, and related data, which I have manually updated. It is a page from the Brown Book. Enclosure 2 is a paper that describes the decommissioning process and applicable regulations.

Enclosure 3 includes a memorandum responding to a question on power reactor expiration dates and a list of all power reactors with additional pertinent information. The reason one cannot find Hallam, Elk River, Piqua, and Bonus

, in this list yet they are in the Brown Bock page, is that these never had operating licenses; they were government-owned and operated by utilities under 10 CFR 115 (no longer exists) with operating authorizations.

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2-Please recognize that Enclosure 3 was prepared in 1985 and additions to the list are necessary; that is why I included Enclosure 4, a listing of licensed power reactors through today.

Call me if I can be of further assistance on X24335.

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Carlos A. Velez, Senior Resource Analyst Planning and Resource Analysis Branch Planning and Program Analysis Staff Office of Nuclear Reactor Regulation

Enclosures:

As stated l

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,- t ENCLOSURE 1 2.26 LICENSED U.S. POWER REACTORS U.S. P0WER REACTORS WITH LICENSES TERMINATED I

I I i 11 INDIAN POINT 1 LICENSED BUT SNUT DOWN PERMAllENTLY l I 2l HALLAM l CONSOLIDATED EDISON i CONSUMERS PUBLIC IPWR I 03/26/62l$PL I l 3l ELK RIVER ~ l RURAL COOPERATIVE POWER ISGR l 08/09/62l$PL l l 41 CVTR lBWR l 11/10/62l$PL l l 51 P!QUA l CAROLINAS-VIRGINIA NUCLEAR POWER IHWR l 11/27/62lSPL l l 61 ENRICO FERMI 1 l PIQUA MUNICIPAL UTILITIES 10MR l 05/16/63lSPL l 1 POWER REACTOR DEVELOPMENT l 71 PATHFINDER l NORTHERN STATES POWER IFBR l 07/11/63lSPL l l 81 BONUS 18WR l 03/12/6415PL l l 91 PEACH BOTTOM 1 l P.R. WATER RESOURCES AUTHORITY IBWR l 04/02/64lSPL l NOTE: 1 PHILADELPHIA ELECTRIC INTGRI 01/12/67lSPL l SIGNIFICANT POWER LICENSE (SPL) = OVER 50X OF RATED POWER.

REACTOR TYPES:

BWR - BOILING WATER REACTOR FBR - FAST BREEDER REACTOR OMR - ORGANIC-MODERATED (POWER) REACTOR~

NTGR - HIGH-TEMPERATURE GAS REACTOR PWR - PRESSURIZED WATER REACTOR HWR - HEAVY WATER REACTOR SGR - SODIUM-GRAPHITE REACTOR 10 HUMSOLDT BAY PACIF{c 6/S d ELECTRIC ggg Of/2f/4,2 fol II Deeszen I e conHoewsAtm EDisow 8*'N' 'R BW 0 6/ot o fdL P

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.,', ENCLOSURE 2

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LICENSED REACTOR DECOP9tISSIONING REA MEETING NOVEMBER 12, 1985 P. B. ERICKSON, U.S. NRC Introduction Decomissioning as defined by the NRC means to remove a facility from service and reduce residual radioactivity to a level that pemits release of the property for unrestricted use and termination of the license.

Three areas of interest in reactor decomissioning are presented in this paper: First, the present and the proposed NRC regulations and guides on decommissioning; Second, the impact of the Nuclear Waste Policy Act of 1982 and; Third. NRC experience in decomissioning licensed power reactors.

Present and Proposed Regulations and Guides The requirements for authorization to dismantle a reactor facility and terminate a reactor license are specified in 10 CFP 50.82. Other sections

of NRC regulations are also applicable during the decomissioning process '

i such as 10 CFR Part 20 Standards for Protection Against Radiation and 10 CFR 50.90, Application for Amendment of License or Constructionr Permit. If spent fuel remains on site,10 CFR Part 70 on Special Nuclear Material and Part 73, Physical Protection of Plants and Materials are applicable. 10 CFR Part 51. Environmental Protection Regulations is applicable and requires an environmental impact statement for the decomissioning of a power reactor.

Regulatory Guide 1.86, "Tennination of Operating Licenses for Nuclear Reactors," enclosed, was specifically written for reactor decomissioning.

l This guide presents alternative methods acceptable for decomissioning, requirements for each alternative and the residual radioactivity requirements for tenninating a license.

l l

Th'e regulations and guides for reactor decomissioning are being revised.

A proposed rule change dated February 11, 1985 would revise requirements with respect to decomissioning of reactors and other facilities. The )

significant changes with respect to reactors are the requirements for funding plans, for funding assurance and for decomissioning plans. )

I As proposed, an electric utility may submit either a decomissioning funding plan or a certification that financial assurance for decomissioning will be provided in an amount at least equs1 to

$100,000,000(1984 dollars). Financial assurance may be provided by a variety of methods including internal reserve.

Three decomissioning alternatives are defined in the February 11, 1985 ,

proposed rule changes. These are DECON, SAFSTOR and ENTOMB. I DECON is an alternative in which all equipment, structures and portions of a facility and site containing radioactive contaminants are removed or decontaminated to a level acceptable for relesse to i unrestricted use within a few years of termination of reactor '

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" SAFSTOR is an alternative in which a facility is placed and

maintained in such condition that it can be safely stored and subsequently decontaminated to levels that pemit unrestricted use, j ENTOM8 is an alternative in which radioactive contaminants are encased in a structurally long-lived material, such as concrete. The entombed structure is appropriately maintained and surveillance is jj continued until the radioactivity decays to a level pemitting unrestricted use. This alternative would be allowable for facilities

,- contaminated with relatively short-lived radionuclides such that all

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contaminants would decay to levels pemissible for unrestricted use

.,n within a period c.f about 100 years. Very long-lived radionuclides in reactor vessels such as niobium-94 and nickel-59 would make this j;,r alternative very unlikely for most power reactors.

' " Regulatory Guide 1.86, "Temination of Operating Licenses for Nuclear Reactors," is being revised to reflect the aforementioned teminology and requirements of the proposed rule change. This revised guide is not expected

<.. to be a significant change from the present guidance.

9 A second regulatory guide titled " Assuring the Availability of Funds for

$d Decomissioning Nuclear Reactors" is being developed in conjunction with

- Its purpose is to provide guidance on methods for the proposed rule.,y complying with the requirements in the rule for submitting c

','t.

, ~, for decomissioning. It will also provide guidance on the fom and l {3, content of acceptable funding methods.

3 ai A third guide, " Format and Content for Nuclear Reactor Decomissioning Plans",

s identifies the infomation needed by the NRC for review and presents a de:

e, format for a licensee's decomissioning plan.

l 7~ , October 1987 due to the many coments received on the proposed The change regulatory guides presented above are expected to be published for comment in about 6 months, t

h Nuclear Waste Policy Act of 1982 3 The Nuclear Waste Policy Act of 1982 (Public Law 97-425, January 7,1983) established a framework for the disposal of high-level radioactive waste

.g. including spent nuclear fuel. The Act provides for a high level waste f repository to be built and operating by 1998. It also established a 1

program for the interim storage of a limited amount of spent nuclear fuel

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at 00E sites while the repository for ultimate disposal is selected and

' developed. The Act stated, however, that the primary responsibility for providing interim storage rests with the reactor licensee. The Act further g, provides that the interim storage would be available to a licensee only if: 1) the licensee cannot reasonably provide adequate spent fuel storage capacity at the reactor site or at another of the licensee's reactors; 2) the

, additional capacity is needed to ensure continued orderly operation of the

,e reactor and; 3) the licensee is diligently pursuing alternatives to the use

,,. of the Federal interim storage.

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  • SAFSTOR is an alternative in which a facility is placed and maintained in such condition that it can be safely stored and subsequently decontaminated to levels that permit unrestricted use.

ENTOMB is an alternative in which radioactive contaminants are encased in a structurally long-lived material, such as concrete. The entombed structure is appropriately maintained and surveillance is continued until the radioactivity decays to a level pemitting unrestricted use. This alternative would be allowable for facilities contaminated with relatively short-lived radionuclides such that all contaminants would decay to levels permissible for unrestricted use within a period of about 100 years. Very long-lived radionuclides in reactor vessels s'uch as niobium-94 and nickel-59 would make this alternative very unlikely for most power reactors.  !

Regulatory Guide 1.86, "Temination of Operating Licenses for Nuclear Reactors," is being revised to reflect the aforementioned teminology and )

requirements of the proposed rule change. This revised guide is not expected to be a significant change from the present guidance.

A second regulatory guide titled " Assuring the Availability of Funds for Decomissioning Nuclear Reactors" is being developed in conjunction with the proposed rule. Its purpose is to provide guidance on methods for complying with the requirements in the rule for submitting cost estimates for decomissioning. It will also provide guidance on the fcm and content of acceptable funding methods.

A third guide, "Fomat and Content for Nuclear Reactor Decomissioning Plans",

identifies the infomation needed by the NRC for review and presents a fomat for a licensee's decomissioning plan.

The final rule changes on decomissioning are not scheduled to be issued until October 1987 due to the many coments received on the proposed changes. The regulatory guides presented above are expected to be published for coment in about 6 ronths.

Nuclear Waste Policy Act of 1982 i The Nuclear Waste Policy Act of 1982 (Public Law 97-425, January 7,1983) l established a framework for the disposal of high-level radioactive waste including spent nuclear fuel. The Act provides for a high level waste repository to be built and operating by 1998. It also established a program for the interim storage of a limited amount of spent nuclear fuel at DOE sites while the repository for ultimate disposal is selected and developed. The Act stated, however, that the primary responsibility for providing interim storage rests with the reactor licensee. The Act further provides that the interim storage would be available to a licensee only if: 1) the licensee cannot reasonably provide adequate spent fuel storage capacity at the reactor site or at another of the licensee's reactors; 2) the ,

additional capacity is needed to ensure continued orderly operation of the reactor and; 3) the licensee is diligently pursuing alternatives to the use of the Federal interim storage, d

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The Waste Policy Act, therefore, dictates that fuel storage will continue at a pemanently shutdown reactor facility until the Federal repository is ready to receive it. The net result of this condition is that nuclear i power reactors will not likely be imediately decontaminated, i.e., the DECON alternative, when they are permanently shutdown because the fuel must remain on site until there is a pemanent repository available.  :

Experience in Licensed Power Reactor Decomissioning About 50 licensed research reactors and critical facilities have been decontaminated and their licenses teminated, DECON, and 6 test reactors have been placed in safe storage, SAFSTOR. Also, three Demonstration power plants, Bonus, Piqua and Hallam have been entombed ENTOMB and one Demonstration power plant Elk River has been decontaminated, DECON. No licensed power reactors have been decontaminated to the point that the license could be terminated. Eight licensed power reactors have been permanently shutdown, however, and have been or will be placed in some form of safe storage, SAFSTOR. Two of these plants, the CVTR, and Pathfinder, are now licensed under byproduct materials licenses with the State of

, South Carolina and the NRC, respectively. The remaining six power reactors

! which retain reactor licenses are addressed below. Present NRC policy and

! the proposed new rules on decomissioning do not provide for the transfer of a reactor facility to byproduct license status. A possession-only reacter facility license would remain in effect during a SAFSTOR period.

Humboldt Bay Power Plant Unit No. 3 The Humboldt Bay Plant Unit 3 is a 220 MW thermal, boiling water reactor that has been shut down since 1976. Units 1 and 2 on the Humboldt Plant site are gas and oil fired. A decomissioning plan and environmental report have been submitted to the NRC. PG&E, the licensee, has selected the SAFSTOR option l for decomissioning. The licensee plans to retain the plant in the safe I storage status for about 30 years after which time the facility would be decontaminated and the license terminated. The 30-year SAFSTOR period

, requires a 15 year extension to the present license. Irradiated fuel will remain in the spent fuel storage pool until a Federal repository is ready

- for its receipt. DOE interim spent fuel storage cannot be used for temporary storage of Humboldt fuel because: 1) there is available storage onsite and 2) the facility is shut down already; therefore, the need "for continued orderly operation of the reactor" is not a factor, i

Indian Point Unit No. 1 l

Indian Point Unit 1 is a 615 MW thermal, pressurized water reactor that has l been shut down since 1974. Consolidated Edison, the licensee, has submitted a decommissioning plan that involves safe storage (SAFSTOR) until Unit 2 is permanently shut down, after which time Unit I would be decontaminated.

Spent fuel will remain in the spent fuel storage pool at Unit No. I until the Federal repository is available.

Dresden Unit No. 1 I Dresden Unit 1 is a 700 MW thermal, boiling water reactor that has been shut down since 1978. The licensee Co intends to select ,,

i l

the SAFSTOR option for decommissioning.menwealth Dresden Unit I w Edison.ill remain in af

All of Unit 1 .

safe storage status until after Units 2 and 3 are shut down.  !

fuel will remain onsite until a Federal repository is available. We expect '

l the licensee to submit a decomissioning plan in 1986.

Peach Bottom Unit No. 1 '

Peach Bottom Unit No.1 is a 115 MW thermal, high temperature gas coolked Peach Bottom Unit 1 is in reactor that has been shut down since 1974.All fuel has been removed from the site an SAFSTOR status now. All liquids and pressurized gases such as the DOE facilities in Idaho.

helium primary coolant have been removed from the facility and the primary coolant system sealed. The radioactive waste processing system and several contaminated cooling systems have been removed from the site and shipped to Accessible surfaces have been

. low level radioactive waste burial sites.

decontaminated. A chain link fence has been installed around the The containment and spent fuel building to establish the exclusion area.

containment building and spent fuel building also have access control through l the use of locked doors. Security for the site is maintained by the security force used for Peach Bottom Units 2 and 3.

Ferst Unit No. 1 Fermi Unit No.1 is a 200 MW thermal, sodium cooled, fast breeder reactor -

Detroit Edison, the licensee, intends to that has been shut down since 1973.

retain Fermi Unit 1 in a safe storage (SAF5 TOR) status until after FermiInUnit 2 is shut down at which time residual radioactivity would be removed.

early 1985 Detroit Edison applied for a 40-year extension to theAll Fermi fuel Unit has 1 possession-only license to accomodate this SAFSTOR period.

been removed from the site as well as the natural uranium blanket assemblies.

The fuel was sent to the AEC Savannah River Plant for reprocessing and the The secondary sodium was free blanket material sent to the AEC Idaho site.

It was barreled in 55 gallon drums and sold comercially.

of radioactivity.

The primary sodium, which was slightly radioactive, was retained on site.

A contract was established with the AEC/00E to accept thisInsodium 1984 thisin 6primary to 10 years for use in its sodium cooled reactor programs.

sodium was barreled and shipped to the DOE Idaho site.

Vallecitos Boiling Water Reactor The Vallecitos Boiling Water Reactor (VBWR) which operated at 50 MW thermal All fuel was shut down in 1963 and placed in a safe storage (SAFSTOR) status.

has been removed from the site, the accessible areas decontaminated and access to the facility controlled through the use of locked doors and security guards.

Conclusions In the past the AEC/ DOE has accepted spent fuel from licensed power DOE reactors for storage and reprocessing when the facility was decomissioned.The Waste continues to accept spent fuel from research and test reactors.

Policy Act of 1982 removes that option, however, for power reactor decomissioning. Storage of spent fuel on site until a Federal repository is ready for permanent disposal must, therefore, be considered by utilities that plan to decomission power reactors before the year 1998. For single unit plants, where security and maintenance costs cannot be shared with operating units, the storage of fuel on site for a long ters could be a significant cost.

8

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ENCLOSURE 4

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OFFICE OF' NUCLEAR REACTOR REGULATION PLANTS FILE REPORTS EXPLANATORY NOTES

1. APPLICABILITY OF NOTES THIS PAGE OF NOTES HAS GENERIC APPLICABILITY TO SEVERAL REPORTS G FROM THE " PLANTS" DATA FILE. AND IS ATTACHED TO ALL THOSE REPORTS:

THEREFORE. CERTAIN REFERENCES MAY NOT BE FOUND IN THE PARTICULA YOU MAY BE READING.

2. VALIDITY OF REPORT PLEASE RECOGNIZE SOME REFORTS APE ISSUED WEEt'LY. OTHERE. AD HOC.

THAT THE DATES SHOWN AFE VALID AS OF THE DAY THE r,EPOFT I3 PUBLI3HED.

NOT AS OF THE DAf THE PCPORT IS READ. WHICH MAY BE WEEt:3 LATER.

'. STAGE DE5CRIPTOPS SD = oHUTDOWN O'i = OF EF A r I NG R _..,c TC; CW = CALEWORt t t . 5. . .

.NDI; OPERAT I;40 LICENIE RE ILW e FERMIT CD = CANCELLED--PLANT HELD A VALIO CONSTRUCTION 4 OL AND FP DATES (5% OR THE OL DATE IS EITHER THE ACTUAL OR E5TIMATED OFERATING LICENSE GREATER) ISSUE DATE. THE FP (FULL-POWER) DATE IS THE DATE OF THE ACTUAL FOWEF OR PROJECTED COMMISSION DECISION TO REMOVE RESTRICTIONS AND PERMIT ASCENSION TO 100*4. AND IS BASED ON THE UTILITY COMFANY ESTIMATE OF CONSTRUCTION COMFLETION.

C = CANCELLED: N = NOT SCHEDULED FOOTNOTES: E = ESTIMATED:

IN THE FORMAT MM/DD/YY THE COMPUTER ONLY ACCEF TS VALID POSSIBLE Tc 1 O LA rIGi , Tl :/. F F Fi.M. 7E '.. *.

DATES '

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i t10 THIP TFENT;! !10NT!;. FOR E t.~ MF L E > . En(S 6 Isif,: T,m A FC.;E.

THC DnTE in1,i.i. W HAS & EN Ci1i D c:!.D W'L.e4- NO '..-LfD 1T 3HOIIL D E:E READ Ai "Ou; N0Wu" GR "auT 6CMIDittFD'

5. SOUf;CE THEIR THIS REPORT USES THE BEVILL/ MONTHLY AND NTOL REPORTS AS BASES:

FLEASE REFER TO THOSE REFORTS FOOTNO TES ARE ALSO APFLICABL E HERE.

FOR COMPLETE INFORMATION.

6. CONTACT FOR OUESTIONS. CHANGES, EXTRA COPICS. ETC.. CONTACT CARLOS A.VELEZ, AT X-24335.

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OFFICE OF NUCLEAR REACTOR REGULATION 1 PLANTS SORTED BY STAGE & OL DATE 08/11/86 13:58:08 BASIS: 07/30/86 BEVILL/ PREPARED BY MTHLY & 07/28/86 NTOL REPT DOCEET PLANT STGE TYPE VEND OL DATE FP DATE 1 50010 Dresden 1 SD BWR GE 06/02/60 Ge/02/60

' 50133 Humboldt Bay ; ED BWR GE 08/28/62 08/08/62 0320 SD PWR BW 02/08/78 02/08/78 NO. OF PMs:

Y 1 50029 Yankee Rowe OR PWR WE 07/09/60 07/29/60 2 50155 Btg RocI Point 1 OR BWR GE 08/!0/62 08/30/62 3 50206 San Onofre 1 OR PWR WE 03/27/67 03/27/67 4 50213 Haddam Ne:6 OR FWR WE 06/30/67 06/30/e7 5 50409 La Crosse OR BWR AC 07/03/67 07/03/67 6 50219 Ovster Creel 1 GR BWR GE 09/01/69 06/01/69 7 50220 Nine Mile Point 1 OR BWR GE 08/22/e9 08/22/69 8 50244 G1nna OR FWR WE 09/16/69 09/16/69 9 50237 Dresden 2 OR BWR GE 12/22/69 12/22/69 10 50261 Robinson 2 OR PWR WE 09/23/70 09/23/70 11 50266 Point Beach 1 OR PWR WE 10/05/70 10/05/70 12 50245 Millstone 1 OR BWR GE 10/26/70 10/26/70 13 50263 Monticello OR BWR GE 01/19/71 01/19/71 14 50249 Dresden 3 OR BWR GE 03/02/71 03/02/71 15 50280 Surry 1 OR PWR WE 05/25/72 05/25/72 16 50250 Turiey Point 3 OR FWR WE 07/19/72 07/19/72 17 50293 Pilgrim i OR BWR GE 09/15/72 09/15/72 18 50 5", Pal 1sades OR FWR CE 10/16/72 10/16/72 19 50254 Duad Cities 1 OR BWR GE 12/14/72 12/14/72 20 50265 Quad Cities 2 OR BWR GE 12/14/72 12/14/72 21 50281 Surry 2 OR PWR WE 01/29/73 01/29/73 22 50269 Oconee 1 OR FWR BW 02/06/73 02 / Co, 73 23 50271 V e r n.o n t Yanlee 1 OR Bn'R GE 02 /28/ T 02/2G/73 24 50001 Point Beach 2 GR i R WE 03/08/73 03/08.73 25 50251 Tur6 ey Pot nt 4 OR PWR WE 04/10/73 04/10/73 26 50309 Maine Yantee OR PWR CE 06/29/73 06/24/73 27 50285 Fort Calhoun 1 OR PWR CE 08/09/73 08/09/73 28 50247 Indian Point 2 OR PWR WE 09/28/73 09/28/73 29 50270 Oconee 2 OR PWR BW 10/06/73 10/06/73 30 50295 Zion 1 OR PWR WE 10/19/73 10/19/73 31 50304 Zion 2 OR PWR WE 11/14/73 11/14/73 32 50277 Peach Bottom 2 OR BWR GE 12/14/73 12/14/73 30 50259 Browns Ferry 1 OR BWR GE 12/20/73 12/20/73 88 NOTE: THIS REPORT IS NOT COMPLETE IF THE COVER / NOTES PAGE IS MISSING v6 1

o c

PLANTS SORTED BY STAGE & OL DATE (Continued) 08/11/86 2 DOCKET PLANT STGE TYPE VEND OL DATE FP DATE 34 50267 Fort St Vrain OR HTG GA 12/21/73 12/21/73 35 50305 Kewaunee OR PWR WE 12/21/73 12/21/73 36 50298 Cooper Station OR BWR GE 01/18/74 01/10/74 37 50331 Duane Arnold OR BWR GE O2/22/74 02/22/74 38 50282 Prairie Island 1 OR PWR WE 04/05/74 04/05/74 39 50289 TMI 1 OR PWR BW 04/19/74 04/19/74 40 50278 Peach Bottom 3 OR BWR GE 07/02/74 07/02/74 41 50287 Oconee 3 OR PWR BW 07/19/74 07/19/74 42 50317 Calvert Cliffs 1 OR PWR CE 07/31/74 07/01/74 43 50260 Browns Ferry 2 OR BWR GE 08/02/74 09/02/74 44 50312 Rancho Seco 1 OR PWR BW G8/16/74 08/16/74 45 50001 Hatch 1 OR BWR GE 10/13/74 10/13/74 46 50333 Fit:patract OR BWR GE 10/17/74 10/17/74 47 50315 Coot 1 OR PWR WE 10/25/74 10/25/74 48 50006 Freirte Island 2 OR PWR WE 10/29/74 10/29/74 49 50313 Artansas 1 OR PWR BW 12/01/74 12/01/74 50 50024 Brunswtch 2 OR BWR GE 12/27/74 12/27/74 51 50336 Millstone 2 OR PWR CE 09/30/75 09/30/75 52 50344 T r o.i a n OR PWR WE 11/21/75 11/21/75 53 50335 St Luc.te 1 GR PWR CE 03/01/76 03/01/76 54 50286 Indian Point 3 OR PWR WE 04/05/76 04/05/76 55 50334 Beaver Valley 1 OR PWR WE 07/02/76 07/02/76 56 50325 Brunswict 1 OR BWR GE 11/12/76 11/10/76 57 50296 Browns Ferry 3 OR BWR GE 11/12/76 11/12/76 58 50018 Calvert Cliffs 2 OR PWR CE 11/30/76 11/30/76 -

59 50272 Salem 1 OR PWR WE 12/01/76 12/01/76 60 50002 Crystal River 3 OR PWR BW 01/28/77 01/28/77 61 50346 Davis-Besse 1 OR PWR BW 04/22/77 04/22/77 62 50348 Farley 1 OR PWR WE 06/25/77 06/25/77 63 50316 Coot 2 OR PWR WE 12/23/77 12/23/77 64 50338 North Anna 1 OR PWR WE 04/01/78 04/01/75 65 50366 Hatch 2 OR BWR GE 06/13/78 06/13/79 66 50368 Arkansas 2 OR PWR CE 12/14/78 12/14/78 67 50327 Sequoyah 1 OR PWR WE O2/29/80 09/17/80 68 50339 North Anna 2 OR PWR WE 04/11/80 08/21/50 s9 50011 Salem 2 OR PWR WE 04/13/80 05/20/51 70 50364 Farley 2 OR PWR WE 10/23/80 03/31/G1

~1 50369 McGuire 1 OR PWP WE 06/12/81 07/08/C1 72 50328 Sequoyah 2 OR PWR WE 06/25/81 09/15/E1 73 50361 San Onofre 2 OR PWR CE 02/16/82 09/07/92 74 50373 La Salle 1 OR BWR GE 04/17/82 08/13/E2 75 50416 Grand Gulf 1 OR BWR GE 06/16/82 11/01/64 76 50387 Susquehanna 1 OR BWR GE 07/17/82 11/12/82 77 50395 Summer 1 OR PWR WE 08/06/82 11/12/82 78 50362 San Onofre 3 OR PWR CE 11/15/82 09/16/93l 79 50370 McGuire 2 OR PWR WE 03/03/83 05/27/83 88 NOTE: THIS REPORT IS NOT COMPLETE IF THE COVER / NOTES PAGE IS MISSING e,

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g-g PLANTS SORTED BY STAGE 8. OL DATE (Continued) 08/11/86 3 DOCV.ET PLANT STGE TYPE VEND OL DATE FP DATE 80 50389 St Lucie 2 OR PWR CE 04/06/83 06/10/03 81 50374 La Salle 2 .OR BWR GE 12/16/83 03/23/84 82 50397 WNP-2 OR BWR GE 12/20/83 04/13/E4 C3 50388 Susquehanna 2 OR BWR GE 03/23/84 06/07/84 C4 50075 Diablo Canyon 1 OR PWR WE 04/19/84 11/02/84 85 50483 Callaway 1 OR PWR WE 06/11/84 10/18/84 86 50352 L i mer i ci: 1 OR BWR GE 10/26/84 08/08/E5 87 50454 Byron 1 OR PWR WE 10/31/84 02/14/E5 88 50413 Catawba 1 OR PWR WE 12/06/84 01/17/85 29 50382 Waterford 3 OR PWR CE 12/18/E4 03/16/E5 90 50528 Palo Verde 1 OR PWR CE 12/31/84 06/01<85 91 50482 Wolf Creel 1 OR PWR WE 03/11/85 06/04/E5 92 50341 Ferm 2 OR BWR GE 03/20/85 07/15/95 93 50323 Diablo Canyon 2 OR PWR WE 04/26/85 08/26/E5 94 50322 Shoreham 1 OR BWR GE 07/03/85 01/01/75 N 95 50458 Rtver Bend 1 OR DWR GE 08/29/85 11/20/05 06 50423 Millstone 3 OR PWR WE 11/25/85 01/01/Em 97 50529 Palo Vssede OR PWR CE 12/09/85 04/24/06 99 50414 Catawba 2 OR FWR WE 02,24/06 05 / l e i a :.

99 50440 Perry 1 OR BWR GE G3/18/06 09/05/Es E 100 50354 Hope Creel OR BWR GE 04/11/8e 07/25/86

/0I GIAL TmI- A - e d %m 4 0s F;ns-g 1 50410 Nine Mlle Point 2 CW BWR GE 08/15/86 E M

1 /30/06 E 2 50461 Clinton 1 CW BWR GE 08/18/86 E 11/15/Bo E 3 50400 Harris 1 CW PWR WE 08/25/86 E 10/25/St, E 4 50456 Braidwood 1 CW PWR WE 09/30/86 E 11/30/E6 E 5 50455 Byron 2 CW PWR WE 10/01/86 E 12/01/Et E 6 50443 Seebrool 1 CW PWR WE 10/30/86 E 01/01/9 9 E 7 50424 Vogtle 1 CW PWR WE 12/01/86 E 12/01/66 E 8 50530 Palo Verde 3 CW PWR CE 03/01/87 E C5/01/87 E 9 50390 Watts Bar 1 CW PWR WE 03/31/87 E 05/31<E? E 10 ",0412 Bes.or V+11ev 2 CW FWR WE 04/01/87 E 06/01.E' E 11 50498 South Te: es 1 CW FWR WE 06/01/87 E 06/01/67 E 12 50341 Wr.tts Bar 2 CW FWR WE 09/30/87 E 11/30.G~ E 13 50445 Comanche Feat 1 CW PWR WE 12/31/87 E O2/28<EE E 14 50457 Braidwood 2 CW PWR WE 01/31/88 E 03/01/53 E 15 50425 Vogtle 2 CW PWR WE 03/01/88 E O!/01/EB E 16 50446 Comenche Peel 2 CW PWR WE - 06/30/88 E 08/01/23 E 17 50499 South Texas 2 CW PWR WE 12/01/88 E O2/01/89 E 18 50353 Limeric6. 2 CW BWR GE 04/01/90 E C5/01/90 E 19 50428 Bellefonte 1 CW PWR BW 01/01/93 E 01/01/93 E 20 50439 Bellefonte 2 CW PWR BW 01/31/95 E 01/31/95 E 21 50460 WNP-1 CW PWR BW 01/01/99 N 01/01/99 N a: NOTE: THIS REPORT IS NOT COMPLETE IF THE COVER / NOTES PAGE IS MISSING i U ,,9 JJ

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PLANTS SORTED BY STAGE & OL DATE (Continued) 08/11/86 4 DOCKET PLANT STGE TYPE VEND OL DATE FP DATE 22 50508 WNP-3 CW PWR CE 01/01/99 N 01/01/99 N ,

23 50417 Grand Gulf 2 CW BWR GE 01/01/99 N 01/01/99 N 23 50441 Perry 2 CW BWR GE 01/01/99 N 01/01/99 N 25 50444 Seabrook 2 CW PWR WE 01/01/99 N 01/01/99 N NO. OF PMs 1 50329 Midland 1 CD PWR BW 01/01/99 C 01/01/99 C 2 50330 Midland 2 CD PWR BW 01/01/99 C 01/01/99 C 3 50426 Vogtle 3 CD PWR WE 01/01/99 C 01/01/99 C 4 50554 Phipps Bend 2 CD BWR GE 01/01/99 C 01/01/99 C 5 50427 Vogtle 4 CD PWR WE 01/01/99 C 01/01/99 C 6 50518 Hartsville Al CD BWR GE 01/01/99 C 01/01/99 C 7 50435 Surry 4 CD PWR WE 01/01/99 C 01/01/99 C 8 50519 Hartsville A2 CD BWR GE 01/01/99 C 01/01/99 C 9 50485 Sterling 1 CD PWR WE 01/01/99 C 01/01/99 C 10 50520 Hartsville B1 CD BWR GE 01/01/99 C 01/01/99 C 11 50516 Jamesport 1 CD PWR WE 01/01/99 C 01/01/99 C 12 50521 Hartsville B2 CD BWR GE 01/01/99 C 01/01/99 C 13 50367 Bailly 1 CD BWR GE 01/01/99 C 01/01/99 C 14 50404 North Anna 3 CD PWR BW 01/01/99 C 01/01/99 C 15 50402 Harris 3 CD PWR WE 01/01/99 C 01/01/99 C 16 50401 Harris 2 CD PWR WE 01/01/99 C 01/01/99 C 17 50355 Hope Creek 2 CD BWR GE 01/01/99 C 01/01/99 C 18 50459 River Bend 2 CD BWR GE 01/01/99 C 01/01/99 C 19 50509 WNP-5 CD PWR CE 01/01/99 C 01/01/99 C 20 50566 Yellow Creek 1 CD BWR GE 01/01/99 C 01/01/99 C 21 50434 Surry 3 CD PWR WE 01/01/99 C 01/01/99 C 22 50567 Yellow Creek 2 CD BWR GE 01/01/99 C 01/01/99 C 23 50405 North Anna 4 CD PWR BW 01/01/99 C 01/01/99 C 24 50546 Marble Hill 1 CD PWR WE 01/01/99 C 01/01/99 C 25 50486 Callaway 2 CD PWR WE 01/01/99 C 01/01/99 C 26 50054 Marble Hill 2 CD PWR WE 01/01/99 C 01/01/99 C 27 50513 WNP-4 CD PWR EW 01/01/99 C 01/01/99 C 28 50484 Tyrone 1 CD PWR WE 01/01/99 C 01/01/99 C 29 50517 Jamesport 2 CD PWR WE 01/01/99 C 01/01/99 C 30 50403 Harras 4 CD PWR WE 01/01/99 C 01/01/99 C 31 50553 Phipps Bend 1 CD BWR GE 01/01/99 C 01/01/99 C 32 50462 Clinton 2 CD BWR GE 01/01/99 C 01/01/99 C 33 50358 Zimmer CD BWR GE 01/01/99 C 01/01/99 C 34 50491 Cherotee 1 CD PWR CE 01/01/99 C 01/01/99 C 35 50492 Cherolee 2 CD PWR CE 01/01/99 C 01/01/99 C 36 50493 Cherotee 3 CD PWR CE 01/01/99 C 01/01/99 C TOTAL PLANT COUNT: 164 U.

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