ML16138A410

Summary of 790718 Meeting W/Util in Bethesda,Md Re B&W Small Break LOCA Analyses

ML16138A410
Person / Time
Site:	Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco, Crane
Issue date:	08/15/1979
From:	Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE
To:	NRC - TMI-2 BULLETINS & ORDERS TASK FORCE
References
TAC-11649, NUDOCS 7909100644
Download: ML16138A410 (31)

Text

10-UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 4X AUG 15 1979 Docket Nos.: 50-269, 270, 287, 289, 302, 312, 313, 346 FACILITIES:

Oconee Nuclear Station, Units No. 1, 2 & 3 Three Mile Island Nuclear Station, Unit No. 1 Crystal River Unit No. 3, Nuclear Generating Station Rancho Seco Nuclear Generating Station Arkansas Nuclear One, Unit No. 1 Davis-Besse Nuclear Power Station, Unit'No. 1 LICENSEES:

Duke Power Company Metropolitan Edison Lompany Florida Power Corporation Sacramento Municipal Utility District Arkansas Power & Light Company Toledo Edison Company

SUMMARY

OF MEETING HELD ON JULY 18, 1979 TO DISCUSS BABCOCK

& WILCOX (B&W) SMALL BREAK LOSS-OF-COOLANT ACCIDENT (LOCA)

ANALYSES (REACTOR COOLANT PUMPS OPERATING VERSUS TRIPPED)

On July 18, 1979, members of the NRC staff met with B&W and representatives of the B&W Owners' Group (TMI-2 Follow-up Subcommittee) in Bethesda, Maryland to discuss preliminary calculations performed by B&W which indicated that, for a certain spectrum of small breaks in the reactor coolant system, continued oper ation of the reactor coolant pumps (RCPs) can increase the mass lost through the break and prolong or aggravate the uncovering of the reactor core. A list of attendees is provided as Enclosure 1 to this summary.

BACKGROUND Subsequent to the accident at Three Mile Island, Unit No. 2 (TMI-2) on March 28, 1979, the Office of Inspection and Enforcement (IE) issued several Bulletins requiring certain actions to be taken by all holders of operating licenses for each operating reactor. Item 4.c of IE Bulletin 79-05A required the licensees for B&W designed pressurized water reactors (PWRs) to revise their operating procedures to specify that, in the event of high pressure injection (HPI) initiation with RCPs running, at least one RCP per loop would remain operating.

Similar requirements, applicable to reactors designed by other PWR vendors, were contained in other IE Bulletins.

Prior to the accident at TMI-2, Westinghouse and its licensees generally adopted the position that the operator should promptly trip all operating RCPs in the LOCA situation. This Westinghouse position, led to a series of meetings between the NRC staff and Westinghouse, as well as with the other PWR vendors, to discuss this issue. In addition, more detailed analyses concerning this matter were requested by the staff. This meeting was arranged to discuss B&W's preliminary calculations concerning the effect of continued operation of the RCPs during a small break LOCA.

770 71670 l2

Meeting Summary -

July 18 w/B&W

-2 DISCUSSION As discussed above, the current emergency procedures being used by all B&W operating plants direct the operators to keep at least one RCP per loop opera ting in the event of a LOCA, provided offsite power is available. B&W pre viously presented analyses which demonstrated that the reactor core would be adequately cooled during a small break LOCA provided either the RCPs remained operating during the entire course of the event or were tripped at the beginning of the accident. At the request of the NRC staff, B&W performed additional analyses, for various break sizes, assuming that the RCPs were operating at the beginning of the accident and were then inadvertently tripped a short time into the accident. These calculations were performed using a six node CRAFT-2 model.

2 2

B&W's calculations showed that-for a range of breaks between 0.025 ft2 and 0.2 ft if RCPs remained operating until the reactor coolant system (RCS) contained a high void fraction and were then tripped, the core would be uncovered for an extended period of time (approximately 600 seconds assuming RCP trip at 90% void fraction and two HPI trains operating).

B&W explained that with RCPs operating, more liquid would be lost through the break than could be injected with the HPI system, thus leading to high void fractions in the RCS.

As long as RCPs remained operating, pumping a two-phase mixture of water and steam, cooling of the core would be insured.

However, once'the RCPs were tripped (either manually or through loss of offsite power) the liquid and steam would separate. If the void fraction in the RCS was approximately 63% or greater at the time the RCPs were tripped, the liquid remaining in the reactor vessel, following the liquid/steam separation, would not be suffic ient to cover the core. A period of time would be needed for the HPI system to pump enough water into the vessel to recover the core. B&W's calculations assumed an adiabatic heat-up of the core of 5oF/Sec. during the period the core was uncovered.

• Under certain conditions, these calculations indicated that 10 CFR Part 50 Appendix K limits would be exceeded.

B&W statqd that the critical break size was bounded by these analyses. Below 0.025 ft the void fraction would not exceed the 63% value 2and thus. if RCPs w.ere tripped, the core would remain covered. Above 0.2 ft, the system would depressurize rapidly enough to insure low pressure injection (LPI) initiation for continued core cooling.

The NRC staff expressed several concerns with the model used for the B&W calculations:

(1) the six node CRAFT-2 model was found to produce void fractions several percent lower than the 23 node model normally used for small break analyses, (2) no liquid carryout was assumed to occur from the core during the reflooding period, (3) a homogeneous void distribution model was used in CRAFT-2 during the time the RCPs were operating. This assumption maximizes the liquid lost through the break and may be overly conservative, and (4) the adiabatic heat-up model used when the core is uncovered may also be overly conservative.

Meeting Summary - July 18 w/B&W

-3 B&W stated that on all of the B&W plants no RCS penetrations exist in that range of break sizes and therefore, felt the probability of a break within the bounds of the analyses was highly unlikely. The staff felt that enough uncertainty existed within the analyses that the bounds of the break size could be greater than that presented in the analyses. In addition, the staff asked B&W if having two pressurizer safety valves stick open would put the plant into a small break LOCA situation that was within the critical break size. B&W stated they would look into this matter.

B&W stated that it would continue to do additional analyses in this area to confirm its preliminary calculations; in addition, if prompt tripping of the RCPs during a LOCA situation would be required, it was investigating the possibility of designing a hard-wired RCP trip which would trip the pumps on initiation of HPI (low RCS pressure-indicative of a LOCA) in conjunction with low RCP current (indicative of a high void fraction in the RCS).

The NRC staff stated that it would review the calculations presented and deter mine the advisability of tripping the RCPs upon indication of a LOCA. The slides used in the presentation are included as Enclosures 2 through 15 of this summary.

A similar analysis was presented by B&W for a main steam line break. The results of that analysis showed that the time RCPs were tripped had little effect on the severity of the accident.

Two additional areas were discussed at the end of the meeting:

(1) Outstanding Information Requirements The list of outstanding information requirements, tabulated by B&W in a letter fr6m J. Taylor (B&W) to R

• Mattson (NRC) dated June 13, 1979, was compared to a list compiled by the NRC staff. The staff stated that it needed information in three areas which were not covered in the B&W letter. These include:

(A) NRC concerns regarding the presence of non-condensible gas within the RCS following a small break LOCA, (B) responses to questions concerning the CRAFT-2 code small break analyses raised by the ACRS (ECCS Subcommittee) June 19, 1979, and (C) the ability of the RCPs to operate in a highly voided reactor coolant system.

The staff agreed that a letter formalizing these commitments would be sent in the near future.

Meeting Summary - July 18, 1979 w/B&W

-4 (2) Analyses.Required in the Next 3 to 6 Months A subgroup of members of the Bulletins & Orders and the Lessons Learned Task Forces has determined that, in addition to the evaluation of small break LOCAs, two additional tasks should be undertaken:

(A) an assessment of the symptoms of inadequate core cooling, and (B) an evaluation of accidents and transients beyond current design analyses.

In both cases, the emphasis should be on information needed for operator training, and information needed for the preparation of improved emer gency procedures. The staff suggested that these programs be completed by December 1, 1979. The B&W Owner's Group stated they would have difficulty meeting this schedule. They plan to meet with the staff in mid-August to discuss progress on the two additional analyses.

CONCLUSIONS Following this meeting, the staff held discussions with the other PWR vendors to pass on the information presented by B&W. Analyses performed by all the vendors (B&W, Westinghouse and Combustion Engineering) supported the tripping of RCPs immediately under LOCA conditions. On July 26, 1979, IE Bulletin Nos.79-05C & 79-06C was issued requiring certain actions to be taken by all holders of operating licenses for PWR facilities. This Bulletin required, as immediate action for all PWR licensees, to revise their operating procedures such that upon reactor trip and initiation of HPI caused by low reactor coolant system pressure the operator will immediately trip all operating RCPs. A copy of this Bulletin is attached as Enclosure 16 to this summary.

R. A. Capra, Project Manager Bulletins & Orders Task Force

Enclosures:

As stated Distribution:

See attached pages

ENCLOSURE 1 LIST OF ATTENDEES Duke Power Company D. C. Holt (Systems Engineer, Licensing)

K. Conody (Manager, Projects & Licensing)

R. Gill (Oconee Head - Licensing)

P. M. Abraham (Nuclear Engineer)

General Public Utilities L. Lanese (Control & Safety Analysis Engineer)

Service Corporation Florida Power Corporation P. Y. Baynard (Assistant Manager -

Nuclear Support Services' Sacramento Municipal Utility District S. Anderson (Nuclear Engineer)

Arkansas Power & Light D. H. Williams (Production Engineer)

Company D. G. Mardis (Production Engineer -

Licensing)

Toledo Edison Company F. Miller (Nuclear Systems Engineer)

Consumers Power T. J. Sullivan (Executive Engineer)

Babcock & Wilcox H. Bailey (Licensing Engineer)

R. E. Ham (Product Line Manager, Engineering Services)

D. Halman (Manager, PlantPerformance Services)

E. R. Kane (Manager, Operating Plant Licensing)

C. E..Parks (Adv. Eng.)

M. A. Haghi (Nuclear Engineer)

G. 0. Geissler (Manager, Generic Licensing Unit)

E. A. Womack (Manager, Plant Design)

NRC B. Sheron (Bulletins & Orders Task Force -

Analysis),

R. F. Audette u

Engineer)

P. H. Tam (ACRS)

D. G. Stampels (ACRS)

E. J. Brown (Structures & Components Standards Branch)

S. L. Wookey (Operating Reactors Branch No. 4)

D. Garner (Project Manager, Rancho Seco)

M. B. Fairtile (Project Manager, Oconee 1, 2, 3)

G. Kelley (Bulletins & Orders Task Force -

Systems)

P. E. Norian (Bulletins & Orders Task Force - Analysis)

W. L. Jensen (Ad.

Eg.

Z. R. Rosztoczy (Bulletins & Orders Task Force Group Leade Analys is)

T. H. Novak (Deputy Director, Bulletins & Orders Task Force R. A. Capra (B&W Project Manager, Bulletins & Orders Task Force)

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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 July 26, 1979 IE Bulletin Nos.79-05C & 79-06C NUCLEAR INCIDENT AT THREE MILE ISLAND -!SUPPLEMENT Description of Circumstances:

Information has become available to the NRC, subsequent to the issuance of IE Bulletins 79-05,79-05A, 79-05B, 79-06,79-06A, 79-06A (Revison 1) and 79-06B, which requires modification to the "Action To Be Taken By Licensees" portion of IE Bulletins79-05A, 79-06A and 79-06B, for all pressurized water reactors,(PWRs).

Item 4.c of Bulletin 79-05A required all holders of operating licenses for Babcock & Wilcox designed PWRs to revise their operating procedures to specify that, in the event of high pressure injection (HPI) initiation with reactor coolant pumps (RCPs) operating, at least one RCP per loop would remain operating.

Similar requirements, applicable to reactors designed by other PWR vendors, were contained in Item 7.c of Bulletin 79-06A (for Westinghouse designed plants) and in Item 6.c of Bulletin 79-06B (for Combustion Engineering designed plants).

Prior to the incident at Three Mile Island Unit 2 (TMI 2), Westinghouse and its licensees generally adopted the position that the operator should promptly trip all operating RCPs in the loss of coolant accident (LOCA) situation. This Westinghouse position, has led to a series of meetings between the NRC staff and Westinghouse, as well as with other PWR vendors, to discuss this issue.

In addition, more detailed analyses concerning this matter were requested by the NRC.

Recent preliminary calculations performed by Babcock & Wilcox, Westing house and Combustion Engineering indicate that, for a certain spectrum of small breaks in the reactor coolant system, continued operation of the RCPs can increase the mass lost through the break and prolong or aggravate the uncover ing of the reactor core.

The damage to the reactor core at TMI 2 followed tripping of the last operating RCP, when two phase fluid was being pumped through the reactor coolant system.

It is our current understanding that all three of the nuclear steam system suppliers for PWRs now agree that an acceptable action under LOCA symptoms is to trip all operating RCPs immediately, before significant voiding in the reactor coolant system occurs.

Action To Be Taken By Licensees:

in order to alleviate the concern over delayed tripping of the RCPs after a LOCA, all holders of operating licenses for PWR facilities shall take the foilowing actions:

IE Bulletin Nos.79-05C & 79-06C July 26, 1979 Page 2 of 3 Short-Term Actions

1. In the interim, until the design change required by the long-term action of this Bulletin has been incorporated, institute the following actions at your facilities:

A. Upon reactor trip and initiation of HPI caused by low reactor coolant system pressure, immediately trip all operating RCPs.

B. Provide two licensed operators in the control room at all times during operation to accomplish this action and other immediate and followup actions required during such an occurence.

For facilities with dual control rooms, a total of three licensed operators in the dual control room at all times meets the require ments of this.Bulletin.

2. Perform and submit a report of LOCA analyses for your plants for a range of small break sizes and a range of time lapses between reactor trip and pump trip.

For each pair of values of the parameters, deter mine the peak cladding temperature (PCT) which results. The range of values for each parameter must be wide enough to assure that the maximum PCT or, if appropriate, the region containing PCTs greater than 2200 degrees F is identified.

3. Based on the analyses done under Item 2 above, develop new guidelines for operator action, for both LOCA and non-LOCA transients, that take into account the impact of RCP trip requirements.

For Babcock &

Wilcox designed reactors, such guidelines should include appropriate requirements to fill the steam generators to a higher level, following RCP trip, to promote natural circulation flow.

4. Revise emergency procedures and train all licensed reactor operators and senior reactor operators based on the guidlines developed under Item 3 above.

5. Provide analyses and develop guidelines and procedures related to in adequate core cooling (as discussed in Section 2.1.9 of NUREG-0578, "TMI 2 Lessons Learned Task Force Status Report and Short-Term Recom mendations") and define the conditions under which a restart of the RCPs should be attempted.

Long-Term Action

1. Propose and submit a design which will assure automatic tripping of the operating RCPs under all circumstances in which this action may be needed. 6 - page 2

IE Bulletin Nos.79-05C & 79-06C July 26, 1979 Page 3 of 3 Schedule The schedule for the short-term actions of this Bulletin is:

Item 1:

Effective upon receipt of this Bulletin, Item 2: Within 30 days of receipt of this Bulletin, Item 3:. Within 30 days of receipt of this Bulletin, Item 4:

Within 45 days of receipt of this Bulletin, Item 5:

October 31, 1979 (as noted in Table B-2 of NUREG-0578, under Item 3).

A schedule for the long-term action required by this Bulletin should be developed and submitted within 30 days of receipt of this Bulletin.

Reports should be submitted to the Director of the appropriate NRC Regional Office with copies forwarded to the Director, Office of Inspection and Enforcement and the Director, Office of Nuclear Reactor Regulation, Washington.

D. C. 20555.

Approved by GAO (R0072): clearance expires 7/31/80.

Approval was given under a blanket clearance specifically for generic problems. 6 -

page 3

Babcock & Wilcox Principal Contacts Listing Mr. William Cavanaugh, III Vice-President, Generation and Construction Arkansas Power & Light Company P. 0. Box 551 Little Rock, Arkansas 72203 Mr. W. P. Stewart Manager, Nuclear Operations Florida Power Corporation P. 0. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Mr. Lowell E. Roe Vice-President, Facilities Development Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Mr. William 0. Parker, Jr..

Vice-President -

Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. J. J. Mattimoe Assistant General Manager &

Chief Engineer Sacramento Municipal Utility District 6201 S Street P. 0. Box 15830 Sacramento, California 95813 Mr. J. G. Herbein, Vice-President Metropolitan Edison Company P. 0. Box 542 Reading, Pennsylvania 19640 Mr. James Taylor, Licensing Manager Babcock & Wilcox Company P. 0. Box 1260 Lynchburg, Virginia

Arkansas Power & Light Company cc w/enclosure(s):

Phillip K. Lyon, Esq.

Director, Technical Assessment House, Holms &.Jewell Division 1550 Tower Building Office of Radiation Programs Little Rock, Arkansas 72201 (AW-459)

U. S. Environmental Protection Agency Mr. David C. Trimble Crystal Mall #2 Manager, Licensing Arkansas Power & Light Company P. 0. Box 551 U. S. Environmental Protection Agency Little Rock, Arkansas 72203 Region VI Office ATTN:. EIS COORDINATOR Mr. James P. O'Hanlon 1201 Elm Street General Manager First International Building Arkansas Nuclear One Dallas, Texas 75270 P. 0. Box 608 Russellville, Arkansas 72801 cc w/enclosure(s) and incoming dtd.:

Mr. William Johnson Director, Bureau of Environmental U. S. Nuclear Regulatory Commission Health Services P. 0. Box 2090 4815 41est 'Iarkha m Street 76w "

Russellville, Arkansas 72801 Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Troy B. Conner, Jr.,

Esq.

Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.

W3ashington, D.C.

20006 Arkansas Polytechnic College Russellville, Arkansas 7280l Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse RiissellvilDe, Arkansas 72801

Duke Power Company cc w/enclosure(s):

Mr. William L. Porter Duke Power Company Post Office Box 2178 Babcock & Wilcox 422 South Church Street Nuclear Power Generation Division Charotte N'oth arolna 2242Su'te 420, 7735 Old Georgetown Road Charlotte, North Carolina 2824220014 J. Michael McCarry, III, Esquire Manager, LIS DeBevoise & Libernan 700 Shoreham Building NUS Corporation 806 5th

tree,

~2536 Countryside Boulevard 806 15th Street, NW ashinqton, D. C.

20005 Clearwaterj Florida 33515 Oconee Public Library cc Wenclosure(s) and incoming 201 South Spring Street dtd.

Walhalla, South Carolina 29691 Office of Iterovernmental Relations 116 W-est J&

~t rcet Honorable Janes 0. Phinney County Supervisor of Ocone County 1113lhaMr, South Carol

.a Bs62 Director, Technical Assessment Division Office of Radiation Programs (4A' -4 59)

U. S. Environmental Protection Agency Crystal Miall *2 ArBineton, VirMinia 20460 U. S. EnvironMental Protection Agency Region CV Office ATTN:

EIS COORDINATOR 345 Courtland CStreet, B.E.

Atlanta, Georgia 303083 U. S. Nuclear Regulatory COFr3ission Pec ion a

n

,Ofcice of Inspection and Inforcement 1T1l: esr.

Francis Jape P.

R

i.

Box 85 SenEca, South Carolina 29678

Florida Power Corporation cc w/enclosure(s):

Mr. S. A. Brandimore Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. 0. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 420, 7735 Old Georgetown Road Mr. Wilbur Langely, Chairman Bethesda, Maryland 20014 Board of County Commissioners cc w/enclosures & incoming Citrus. County Iverness, Florida 36250 dd IveressFlorda 3250Bureau of Intergovernmental U. S. Environmental Protection Agency 660 Apalachee Parkway Region IV Office ATTN:

EIS COORDINATOR 345 Courtland Street, N.E.

Atlanta, Georgia 3U308 Director. Technical Assessnent Division Office of Radiation Programs (AW-459)

U. S. Environmental Protection Agency Crystal Mall #2 Arl ington, Virginia 20460 Crystal River Public Library Crystal River, Florida 32L.29 Mr.

R.

Shreve The Publi'c Counsel Room 4 Holland Bldg.

Tallahassee, Florida 32304 Administrator Department of Environmental Regulation uocleaer Plant SitinG Section State of Florida Beontaouery Building 2562 Executive Center Circle, E.

TalTlahassee, Florida d

331 Attorney fleneral Cs R Lenal ffairs Tallahassee, Florida 32301

Metropolitan Edison Company cc w/enclosure(s):

G. F. Trowbridge, Esquire Dauphin County Office Emergency

.Shaw, Pittman, Potts & Trowbridge Preparedness 1800 M Street, N.W.

Washington, D. C. 20036 Cot House reets GPU ervie CoporaionHarrisburg, Pennsylvania 17101 GPU Service Corporation Richard U. Heward, Project Manager Mr. T. Gary Broughton, Safety and Department of Environmental Resources Licensing Manager ATTN:

Director, Office of Radiological 260 Cherry Hill Road Hea I Parsippany, New Jersey 07054 Post Office Lu,.. 2063 Pennsylvania Electric Coripany Mr. R. W. Conrad Director, Technical Assessment Vice President, Generation Division 1001 Broad Street Officeof Radiation Programs Johnstown, Pennsylvania 15907 (AW-459)

U. S. Environmeintal Protection Agency Miss Mary V. Southard, Chairman Crystal Mall F2 Citizens for a Safe Environment Arlington, Virginia 20460 Post Office Box 405 Harrisburq, Pennsylvania 17108 Mr. Robert B. E-rsun Babcock & Wilcox Governrient Publications Section Nuclear Power Generation Division State of Library of Pennsylvania Suite 420, 77H_ Old Georgetown Road Box 1601 (EGucation Building)

Bethesda, a-ylarij 20014 Harrisburg, Pennsylvania 17126 cc w/enclosure(s) and incoming Dr. Edward 0. Swartz dtd.

Board of Supervisors Londonderry Township Governor's Office of State Planning RFD=l - Geyers Church Roan and Development rliddletown, Pennsylvania 17057 ATTN:

Coordinator, Pennsylvania State Clearinghouse U. S. Environmental Protection Agency P. 0. Box 1323 Renion III Office Harrisburg, Pem1slvania 17120 EIS COORPDINIATOR Curtis Building (Sixth Flcor) othl ana Walnut. Streets Hrsradelphia, PennsvlvaniP v

1106

Sacramento Municipal Utility District cc w/enclosure(s):

David S. Kaplan, Secretary and Mr. Frank Hahn General Counsel California Energy Commission 6201 S Street 1111 Howe Avenue P. 0. Box 15830 Sacramento, California 95825 Sacramento, California 95813 Ms. Eleanor Schwartz Sacramento County California State Office Board of Supervisors 600 Pennsylvania Avenue, S.E., Rm. 201 827 7th Street, Room 424 Washington, D.C.

20003 Sacramecnto, California 95814 Docketing and Service Section California Energy Commission Office of the Secretary ATTN:

Librarian U. S. Nuclear Regulatory Commission 1111 Howe Avenue Washington, D.C.

20555 Sacramento, California 95825 Michael L. Glaser, Esq.

Business and Municipal Department 1150 17th Street, N.W.

Sacramento City-County Library Washington, D.C.

20036 828 I Street Sacramento, California 95814 Dr. Richard F. Cole Atomic Safety and Licensing Board Director, Technical Assessment Panel Division U. S. Nuclear Regulatory Commission Office of Radiation Programs Washington, D.C.

20555 (AW-459)

U. S. Environmental Protection Agency Mr. Frederick J. Shon Crystal Mall #2 Atomic Safety and Licensing Board Arlington, Virginia 20460 Panel U. S. Nuclear Regulatory Commission U. S. Environmental Protection Agency Washington, D.C.

20555 Region IX Office ATTN:

EIS COORDINATOR Timothy V. A. Dillon, Esq.

215 Fremont Street Suite 380 Sen Francisco, California 94111 1850 K Street, N.W.

Washington, D.C.

20006 Mr. Robert B. Borsum Babcock & Wilcox James S. Reed. Esquire Nuclear Power Generation Division Michael H. Remy, Esquire suite 420, 7735 Old Georgetown Road Reed, Samuel & Remy Bethesda, Maryland 20014 717 K Street, Suite 405 Sacramento, California 95814 Christopher Ellison, Esquire Dian Grueneich, Esquire California Energy Commission 1111 Howe Avenue Sacramento, California 95825

Sacramento Municipal Utility District cc w/enclosure(s):

Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Mr. Richard D. Castro 2231 K Street Sacramento, California 95814 Mr. Gary Hursh, Esq.

520 Capital Mall Suite 700 Sacramento, California 95814 cc w/enclosure(s) and incoming dtd.:

California Department of Health ATTN:

Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 94814

Toledo Edison Company cc w/enclosure(s):

Mr. Donald H. Hauser, Esq.

Director, Technical Assessment The Cleveland Electric Division Illuminating Company Office of Radiation Programs P. 0. Box 5000 (AW-459)

Cleveland, Ohio 44101 U. S. Environmental Protection Agency Crystal Mall #2 Gerald Charnoff, Esq.

Arlington, Virginia 20460 Shaw, Pittman, Potts and Trowbridge U. S. Environmental Protection Agency 1800 M Street, N.W.

Federal Activities Branch Washington, D.C. 20036 Region V Office ATTN: EIS COORDINATOR Leslie Henry, Esq.

230 South Dearborn Street Fuller, Seney, Henry and Hodge Chicago, Illinois 60604 300 Madison Avenue Toledo, Ohio 43604 Mr. Samuel J. Chilk, Secretary U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum Washington, D.C.

20555 Rabcock & Wilcox Nuclear Power Generation Division The Honorable Tim McCormack Suite 420, 7735 Old Georgetown Road Ohio Senate Bethesda, Maryland 20014 Statehouse Columbus, Ohio 43216 Ida Rupp Public Library 310 Madison Street The Honorable Tim McCormack Port Clinton,Ohio 43452 170 E. 209th Street Euclid, Ohio 44123 President, Board of County Commissioners of Ottawa County Mr. Lowell E. Roe Port Clinton, Ohio 43452 Vice President, Facilities Development Attorney General Toledo Edison Company tepartment of Attorney General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Harold Kahn, Staff Scientist Bruce Churchill, Esq.

Power Siting Commission Shaw, Pittman, Potts & Trowbridge 361 East Broad Street 1800 M Street, N.W.

Columbus, Ohio 43216 Washington, D.C.

20036 Docketing and Service Section Atomic Safety &.Licensing Board Panel Office of the Secretary U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Washington, D.C.

20555 Atomic Safety and Licensing Appeal Panel U. S. Nuclear Regulatory Commission Washington, D.C.

20555

• e 4

Toledo.Edison Company cc w/enclosure(s):

Ivan W. Smith, Esq.

Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C..

20555 Dr. Cadet H. Hand, Jr.

Director, Bodega Marine Laboratory University of California P. 0. Box 247 Bodega Bay, California 94923 Dr. Walter H. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830 Ms.

Jean DeJuljak 381 East 272 Euclid, Ohio 44117 Mr. Rick Jagger Industrial Commission State of Ohio 2323 West 5th Avenue Columbus, Ohio 43216 cc w/enclosure(s) and incoming dtd.:

Ohio Department of Health ATTN:

Director of Health 450 East Town Street

Columbus, Ohio 43216