ML20046B185

Direct Testimony of Ga Harrison,Bm Cohn & RB Barnes Re Contention 17,Kaowool as Fire Barrier for Cable Trays

ML20046B185
Person / Time
Site:	Hatch, Zimmer
Issue date:	10/30/1979
From:	Harrison G NRC
To:
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ML20046B176	List: ML20046B175 ML20046B180 ML20046B185 ML20046D316
References
NUDOCS 9308030249
Download: ML20046B185 (23)

Text

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October 30, 1979 1

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

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BEFORE THE ATOMIC SAFETY AND t.ICENSING BOARD 7

In the Matter of CINCINNATI GAS & ELECTRIC COMPANY

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Docket No. 50-351 (Wm. H. Zimer Nuclear Power. Plant)

Direct Testimony of Gregory A. Harrison Bert M. Cohn, and Robert D. sarnes Recardine Contention No.17 Kaowool As A Fire Ba'erier For Cable Trays o

Gregory A. Harrison hereby states as 'follows:

I am. employed as a Fire Protection Engineer in the Auxiliary Systems Branch, Division of Systems Safety.. Nuclear. Regulatory Commission.

Bethesda, Maryland.. My educational and Professional qualifications are set forth imediately below:

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Education B.S. Fire Protection Engineering, University of Maryland 1966; M.S. Civil 1

Engineering, University of Maryland 1970; and M.S. Engineering Admini,-

stratien, George idashington 1979. I have received a certificate'from Cak-Ridge University covering the Radiation Safety Training Program.

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addition. I hold professional engineering registrations in California and i

Maryland in fire protection and civil engineering.

I belong to the Society of Fire Protection Engineers, the National Fire Protection Association and have j

authored numerous publications.

Exoerience I joined the USNRC in August,1977 as a fire protectiott engineer. In this 1

capacity I have perfomed inspections of power reactors during the con-struction stage to ascertain confomity with fire protection criteria, including the Zimer facility; evaluated the adequacy of licensees' fire protection programs and its relation to the safety of operations. Finally, I have prepared fire

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protection sections of the Staff's safety evaluations, for both BWR and PWR plants including the Zimmer facility, the appropriate pages of which are attached.

hereto and made a part of this testimony.

Prior to, joining the Comission I worked two years for the Arabian American l

011 Company (ARAMCO) in Dhahran, Saudi Arabia. I held the position of Chief, i

Fire Protection Engineer for the Facilities Engineering Division.

1 From January,1973, to July,1975, I worked for the National Bureau of j

5tandards in Gaithersburg, Maryland as fire protectiam syineer in fire l

research testing.

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From July,1969, to January,1173, I worked 'as al general engineer with j

.l the Naval Ship Engineering, Center, Washington, D.C.

From May,1967, to July,1961, I worked as a fire protection engineer'for -

NASA at Goddard ' Space Flight Center, Greenbelt Maryland.

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3 Bert M. Cohn hereby states as follows:

I am a consulting engineer specializing in fire protection and safety, building code analysis, and physical security by Gage-Babcock & Associates (GBA),135 Addison Ave., Elmnurst, Illinois, where I hold the positions of Senior Vice President and Treasurer.

GBA is a consulting firm specializing in fire testing and fire protection. GBA is under contract with the U.S. Nuclear Regulatory Coernission to provide technical assistance for nuclear power plant fire protection program reviews and evaluations. GBA has been providing fire protection consulting services and technical assistance to NRC since 1976. I have been the project director for a major portion of this work.

Robert D. Barnes of GBA who works under my direct supervision is the project engineer for the Zimer Nuclear Power Station.

Education and Excerience of Bert M. Cohn I have a B.S. in Fire Protection and Safety Engineering Illinois Institute A

of Technology,1952 and awRegistered Professional Engineer in Illinois, New A

Jersey, New York Virginia, and Alabama.

I a:n a Certified Protection Professional (American Society for Industrial Security)'and Certified Fallout Shelter Analyst (Federal Emergency Management Agency).

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4-I have been~ emp7oyed by Gage-Babcock & Associates since 1977 as Senior r.ngineer and fire protection and safety consultant. My major activities have been in the area of (1) life safety code compliance surveys of institutional properties, (2) design of fire detection systems (3) municipal fire department evaluatiens, and (4) nuclear power plant fire protection program reivew and evaluatien.

Prior tnereto I was employed by Insurance Services Office, Wiscensin (1969-75), National Fire Protection Association Boston (1975)

Insurance Company of North toerica, Midwest Region (1975-76), and Veterans Administration Wood, Wisc. (1976-77).

I am a member of Society of Fire Protection Engineers, American Society 'of Safety Engineers, American Society for Industrial Security, and American Society for Testing and Materials; Chaiman of subcomittee on Coubustibility standards.

ASTM Comittee E5 on Fire 5tandards; Member of Record Protection and Firtsafety SyhSols comittees, National Fire Protection Association; and Chaiman of Board of Fire and Police Comissioners City of Elmhurst, Illinois.

I have lectured 'at college and professional symposia and have been a frequent speaker at professional society meetings and conferences, and authored numerous articles and reports.

I have been employed by wage-Babcock & Associates since 1957; its vice presideat since 1963 and treasurse since 1968.

I have participated in and directed hundreds of projects, including design and specification of detection, alarm and i

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fire extinguishing syste:ns; risk analysis studies in industrial and institutional properties; loss investigations of equipment failures, fires and explosions; systems analysis for code trade-offs and equivalencies; and research and testing.

Prior to being employed by GBA I was employed by the U.S. Ar:ry Forcas Far East in Japan and Korea as chief of fire protection sections (1955-57) and served in the U.S. Army in fire protection engineering positions at the Army Engineer Research & Development Laboratories and Army Forces Far East headquarters (1953-55).

Robert D. Barnes hereby states as follows:

Education and Excerience, I have a B.S. in Fire Protection Engineering, Illinois Institute of Tecnnology, 1969. Registered Professional Engineer in Wisconsin.

I am a member of the Society, of Fire Protection Engineers.

I have been employed by GBA as a fire protection engineer since 1976 specializing in reviewing fire hazard and fire

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pcotection programs for nuclear power plants. I work under the direct supervision of Bert M. Cohn, Prior to being employed by GBA I, worked in fire protection -

analysis for several insurance companies.

I have witnessed tests of Kaowool and am familiar with its fire resistant properties.

The Miami Yalley Power Project has raised Contention 17, regarding fire protection, which is set forth at length below.

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i' contention 17

-I Fire insulation material which is being used to i

protect the cables in the cable trays from fire is

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inadequate to protect the cables in light of the cable tray installation design and cable tray load.

The tests.cf the fire insulation material were

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improperly performed in that conditions which will exist during cperation were not adequately simulated.

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This matter is addressed in the fire protection section of the Staff's Supple-ment No.1 to the Safety Evaluation, the two pertinent pages of which are j

attached hereto and made a part cf this testimony. In further amplification of the protective value of Kaowool we s' tate as follows.

q Mr. Cohn and Mr. Barnes are associated with Gage-Babcock & Associates, Inc.

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and act as consultants to the NRC in the evaluation of fire protection programs for nucl.:ar power plant's.. Messrs. Robert D. Barnes and Bert 1

Cohn have participated in the NRC review and evaluation. of the adequacy of fire _ afety measures to be incorporated. in the.Iimmer Nuclear Power j

s Station including measures to protect electrical. cables and cable trays.

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-This work was done for and in close cooperation with the staff of Division of Systems safety, NRC and in particular with Mr. Greg Harrison of the NRC. Using'NRC guidelines (57p g.5-1) and natio'nally recognized fire.

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protettion standards, Mr. Barnes and Mr. Harrison reviewed the fire _ pro.

i taction avaluation' report submitted by the appiteant for the-Zimmer p1_ ant. _

provided_ comments, questions, and evaluations 'as :to the' adequacy of the fire protection features and tests, and performed.an on-site, 3-day.

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! i survey at Zimmer, attended meetings with the applicant to resolve differences as to the need for protective measures. Mr. Cohn's invol ve-ment with Zimmer was periodically to review the progress of Mr. Barnes' i

review and assist in resolving technical issues.

In addition, Mr. C hn l

i witnessed, at the request of the NRC, the test of Kaowool as fire protec-tive insulating material on cable trays by Portland Cement Association at their Construction Technology Laboratories on June 6,1979, a copy of which is appended to this testimony.' This* report was written by Melvin

5. Abrams. All of us, Messrs. Cohn, Barnes, and Harrison recognize W. Abrams as an acknowledged expert in the testing of fire resistant unterial s.

The test procedures. equipment, and results are, based on our professiona knowledge and expertise, accurately set forth in the report authored by Mr..Abrams. We fully concur in the conclusions reached by Mr. Abrams that the Xaowool material and the design tested offers a 1-1/2 fire resistant rating for cable trays.

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Dur principal concern in the review and evaluation process is to assist the NRC ta assure that$ an adequate level of fire protection is provided in areas where wiring and equipment serve safety equipment and could be-sobject to damage from a single fire incident. In the situation of cable trays, the location of each tray to the other, the location of trays within the space, the separation ~ between redundant divisions,- the presence of materials and' equipment creating a fire exposure, the acces-sibility.of the' space for firefightinf, the presence of fire detection and fire suppression equipment,' and other factors are considered.in j

establishing whether additional protective measures, such as.-fire barriers or-insulatior) are required, and if so, what those additional i

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.s-These determinations are made protective measures should be.

based upon our expertise in this situation. Both Messrs Barnes ard l

Harrison have inspected the Zimmer facility.

4 For Zimer, Barnes detersined, with Mr. Harrison concurring, that there i

The were several areas requiring additional measures of protection.

applicant has agreed to the installation of fire barriers,-protective insulation, automatic sprinklars, or' combinations thereof in those places recommended by Barnes and Harrison for additional protection; The applicant prepased to use Kaowool as a protective insulation material upon cable trays and conducted tests to show its adequacy for i

the purpose (Revision 12 to Zimmer Fire Protection Evaluation Report).

l Both Mr. Cohn and Mr. Barnes recommended to the NRC staff that these l

tests be rejected because they did not simulate standard ASTM E119 fire u

In a memo to the Zimmer proj.ct manager dated April 19, _

i test. conditions.

i 1979, from Stoltz to Bergman, the.NRC staff stated that all fire tests -

todate submitted by' Zimmer did not support a 1-1/2 hour fire rating and, q

hence, an open ites existed,.(see staff legal filing 5/7/79).

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An additional test was then_ scheduled by Zimer, at the request of-the j

NRC, to be conducted under standard test conditions, using the ASTM 1

E119 procedures, at PCA Laboratories. Mr. Cohn reviewed the test pro-cadures and equipment prior to.the test and was satisfied that the test.

l would represent _ at least as severe a. condition as could reasonably: be.

PCA-envisioned under actual use conditions in the Zimmer facility.

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Laboratories and its manager of the fire research section~ (Mr. Abrams)-

are known by us to be experts, thoroughly familiar with standard fire

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test procedures and able to conduct such tests impartially and objec-q tively. This test, using four fully loaded cable trays, each indivi-dually wrapped with Kaowool insulation, was conducted on June 6,1979.

Every few minutes during the test, Mr. Cohn checked the temperature l

recorders and observed the test specimens in the furnace for indications i

of premature failure. There were none. The protected trays successfully resisted the effects of the exposure fire for a period of not less then t9 90 min. This test is described in the report by Melvin 5. Abrams, entitled

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" Fire Protective Cable Tray Fire Test," dated June,1979, copy' attached

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hereto. Mr. Cohn subsequently submitted his approval to the NRC via a '

letter " Fire Test of Cable Trays, If'uner Nuclear Power Station,"- dated 12 June 1979. Although the cables did not carry full electrical loads.

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which would liberate some heat internally to the trays, we know that this.

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m parameter is not a major one because the issue involves an external fire il exposure. The degree to which energized _ cables'could hasten a test failure is well within the range of the normal: variances one could expect from.

ll tests of this nature and, hence, externally minimal,' e.g.' a few minutes.-

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We are familiar with the fire tait' conducted under the ' auspices of Sandia

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Laboratories at Underwriters Laboratories on September 15, 1978, reported 7

in. NUREE/CR-0596, A Preliminary Report on Fire Protection. This test was.

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-j to demonstrate the effectiveness of Kaowool and automatic sprinklers -

1 in protecting _ cables in vertical cable trays. We assisted in develo' ping;-

q some of the criteria for. this test. - The fuel, 2 -pal. of a' flammable -

d liquid (heptane), was poured on the floor, and some of it seeped under M'

and through the' Kaowool which was wrapped around the vertical cable tray.

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Because of this; some of the heptane burned within and inside tne Kaowool blanket and damaged some of tLe electrical cables. The Kaowool is totally noncombustible [ composed primarily of silica and alumina compounds (5102 and A10 )], cannot turn, and did not contribute to the fire. The effectivin-23 ness of this material as a fire protective insulatica was not challenged by this test, and it did not fail. Ja adhesive matarial and a simple curb or sheet metal shield around the base of the insulating material would have prevented the liquid from seeping under and into the insulation. The applicant has agreed to provide curbs or shields and an adhesive coating wherever this situation exists at Zimmer.

e The fire protection Section IV SER Supplement No.1 (copy attached hereto) for Itemer states that the PCA fire test conclusively demonstrates the adequacy of the Kaowool design and that Kaowool is acceptable as a fire barrier. All of us signing this testimony concur with that conclusion, We further conclude that a 1 inch layer of Kaowool wrapped around a cable tray will provide a 30-minute effective fire resistant barrier, a 2 inch will provide a 60-minute barrier, a.'J inch will provide a 90-minute barrier. By an effective barrier, we mean that the cables contained in e

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the tray will brable to perform their function without failure for l,';

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Bert M. Conn

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6 Robert D. Barnes-l

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I Dated at Bethesda, Maryland.

this 30th day of October,1979.

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UNITED STATES OF AMERICA

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NUCLEAR REGULATORf CCMMISSION~

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. '8EFORE TRE ATOMIC SAFETY AND LICENSING BOARD s

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In the Matter of.

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1 CINCINNATI $*S'ANDELECTRIC

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Dockat No. 50-358 COMPANY,' e,3, 4,1,..

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4(2n. H. Ztmer Nuclear Power p

.f Station Unit No.41) i i

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CERTIFICATE OF SERVICE A

I nereby certify that copies of " Direct Testimony of Teregory A. Harrison.- Bert M..

Conn, and Robert D. Barnes;Regarding Contention No.17. Kaowool As A Fire. Barrier For Cable Trays" and " Direct Testimony.of Frederice Maura Regarding MetalL j

Chips in Control Rods" in the above-cactioned prra og have been' served on-1 the following by deposit in the United States ma.

N nt class, or, as indicated

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byL an asterisk by deposit in the Nuclear Regulator,, ommission internal mail j

system.i this' 30th' day. cf October,1979:

Chairles Bechhoefer; Esq., Chainnan*

Leah S. Kosik. Esq.

Atomic Safety and Licensing 3454 Ccenell Place

, Board Panel Cincinnati, Ohio. 45220 U.S. Nuclear Regulatory Connis'sion L

j Washington. D.C.

2D555 W. Peter Heih. Esq.

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Assistant City Solicitor Dr. Frank F. Hooper Room 214. City: Mall '

School of Natu.-al Resources Cincinnati, Ohio < 45220 University of Michigan Ann Arbor Michigan '48109 Timothy S. Hogan,i Jr..,Chainnan Board of Comissioners,

Mr. Glenn 0. Bright %

-50 Market Street:

Atomic Safety and Licensing Clennent County Board Panel' Batavia. Ohio 45103-

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U.S. Nuclear Regulatory Conni:Sion

' John D. Woiiver, Esq.

Washington. D.C. '20555

. Clermont County Comunt':y Council-e Box 181

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Troy B. Conner. Esq.,

Conner. Moore and Cerber Batavia, thio 45103 1747 Pennsylvania Avenue, N.W.

. Washington. D.C.

20006

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William J. Moran, Esq.

Atomic Safety and Licensing

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General Counsel Appeal Board" Cincinnati Gas & Electric Co=pany U.S. Nuclear Regulatory Comission P.O. Box 960 Washington, D. C.

20555 Cincinnati, Ohio 45201 Docketina and Service Section*

Atomic Safety and Licensing Offica of the Secretary Board Panel

• U.S. Nuclear Regulatory Comission U.'$. Nuclear Regulatory Comission Washington, D. C.

20555-Washington, D. C.

20555 David Martin. Esq.

Office of the Attorney Genersl 209 St. Clair Street First Floor Frankfort. Kantocky 40601 l

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Cnarles A. Bartn Counsel for NRC Staff k

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cm c.:.w+: 3 UL Underwriters Lab 0ratories Inc.*

eer.: n:suc May 18, 1992 Thermal Ceramics Ms. Vicki C. Floyd P.O. Box 923 Augusta, GA 30903 Our

Reference:

File R11044, Project 84NK8356

Subject:

Electrical Circuit Protective Systems

Dear Ms. Floyd:

This is in responce to our telephone conversation of May 13, 1992 concerning the above subject.

Under Project 84NK8356, File ~R11044, a floor assembly consisting of various types of electrical circuit protective systems was subjected to a fire exposure and hose stream test in accordance with the Outline of Investigation, " Fire Tests For Electrical' Circuit Protective Systems," Subject 1724.

The results of this investigation were forwarded to Thermal Ceramics in our Report dated March 22, 1985.

We understand that Thermal Ceramics requested UL to determine which thermocouples malfunctioned in System No. 8 during the fire exposure test.

The thermocouple location on the cables for System No. 8 is shown in ILL. AB.

A copy of the temperature data for this system is attached for your information.

Thermocouples Nos. 183, 187, 190, 191, 192,~193, 197, 198 and 199 recorded temperatures that were decreasing during the fire exposure test.

The cause of the decreasing temperatures was either the thermocouple wires within the thermocouple plug were reversed or the two wires within the plug were touching each other.

This situation was corrected during the test and the temperature readings increased.

At this time, we cannot account for the sudden decrease in temperature for Thermocouple Nos. 203 through 206 at the end of the fire exposure test.

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R11044 Page 2 -

May 18, 1992 A:pc/15644/L4781-If you have any questions, please contact the writer.

Very truly yours, Reviewed by:

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. um ALEC HAUSER (Ext. 3017)

RICHARD N. WALKE (Ext. 3084)

Senior Project Engineer Engineering Group Leader Engineering Services Engineering Services Department 411 Department 411 A9:pc a:R11044.MAY w

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4: 0 63.5 63.9 63.8 63.3-63.8.;

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30:50 66.6 70.1 76.4 176.21 94.0.

32:50 69.4 72.8 81.4.

177.0 97.5 34:50 68.5 71.6 82.6 219.5 97.4 36:50 71.2 73.4 88.1 231;2 102.1-38:50.

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CHAN(NOS.)

196 197 198 199 200 TIME 0: 1 65.2 63.0 G5.7 63.4 50.8 2: 0 64.8 G2.4 65.7 G3.2 43.3 4: 0 G4.8 62.8 65.8 63.4 44.0 G: 0 G4.7 G3.3 GS.8 63.7 44.8 8: 0 64.5 62.7 65.6 G3.1 7.0.5 -

10: 0 64.8 G3.4 65.9 63.4 80.B 12: 0 64.8 62.2 66.0 62.5 88.7,

14: O' 65.4 61.7 SG.G G2.2 95.9 18:51 70.4 63.7 68.8 64.0 116.8 20:50 7G.2 63.3 70.4 G4.2 109.1 22:50 113.2 62.3 72.1 63.3 116.0 24:50 115.9 G0.G 74.3 G1.9 123.6 2G:50 115.7 58.2 77.6 59.7 143.3 28:50 120.4 58.8 82.1 59.9 163.2 30:5'O 132.5 61.5~

86.4 62.6 377.7 32:50 136.8 63.4 90.7 64.4 302.2 34:50 142.7 51.2 95.2 56.8 379.6 3G:50 147.7 49.3 101.9 55.5 385.4 38:50 150.9 41.5 105.6 48.5 391.8 40:50 156.9 0.8 111.1 9.4 364.9 42:50 172.9

-13.4 117.6

-5.0 349.9 44:49 185.4 0.9 129.6 7.4 327.7 46:49 189.3-12.5 134.9 17.4 307.7 48:49 190.6 37.4 139.6 41.2 306.9-50:49 193.6 92.5' 153.5 0.0 312.4 52:49 195.4 113.4 166.2 116.7 341.8 54:49 196.8 124.9-178.2 129.7-381.7 5G:49 198.9 135.6 191.0 141.5 430.3' 58:49 200.9 148.1 203.0 173.2 513.8 60:50 205.9 162.4 205.5 182.3

'588.1

o FILE R11044-1 ILL. NO.

A49 RARinrK R kRlrOX 84NK8356/R11044 9/26/84 DEGREES E CHAN(NOS.)

202 203 204 205 206 T IME 0: 1 G8.8 G8.9 51.7 51.1 50.5 2: O G8.1 GB.6 43.6 43.0 42.9 4: 0 67.8 68.3 44.7 43.8 43.1 6: 0 G7.6 68.2 44.7 44.4 44.5 8: 0 67.4 68.1 71.8 71.2 69.2 10: 0 GG.9 68.3' 84.3 83.G 76.8 12: 0 G7.3 G8.7 90.1 89.3 79.6 14: 0-G.7.3 69.3 98.0 97.4 94.7 18:51 68.4 72.5 111.3 111.7 118.5 112.4 20:50 69.5 74.4 94.0 94.8 22:50 72.8 76.3 91.4 92.4 117.2 24:50 79.0 78.8 88.5 89.7 122.0 2G:50 92.2 81.G 91.1 92.4 134.3 28:50 105.1 85.1 94.5 95.9 147.0 30:50 123.4 90.1 100.9 102.1 159.6 32:50 127.5 95.6 106.6 107.5 168.3 34:50 132.8 101.2 113.8 114.2 17 G. 0 -

36:50.

137.0 117.0 129.0 128.5 190.5 38:50.

135.2 122.2 137.3 136.0

.197.0 40:50 138.9

,132.9 147.4 144.8 199.1 42:50 137.5' 140.4 150.7 146.0 196.5 44:49 139.6 159.0 166.4 159.6 205.6 46:49 141.3 164.0 173.4 166.0 206.9 48:49 144.5 186.2 189.6 181.8 218.8, 50:49 148.2 322.0 317.8 310.7 341.4 52:49 152.1 408.8 391.2 389.0 412.7.

54:49 154.2 500.0 475.0 482.2 497.2:

5G:49 158.2 574.5 575.2 584.G 588.5 58:49 164.7 416.1

~G57.7 667.0 6G4.0; 60:50 163.5 287.1 354.0 371.2 3G3.5!

9

FILE R11044-1 ILL. NO. A50 RARrork R WTirnY 84NK8356/R11044 9/26/84

~

DEGREES F CHAH(NOS.)

207 208 209 210 211 TIME 0: 1 68.8 68.6 68.9 69.0 69.0!

2: 0 G8.7 G8.5 G8.8 G8.9 G9.0 4: 0 68.5 68.2 68.5 G8.8 68.9:

6: 0 G8.5 G8.3 G8.5 68.9 69.01 8: 0 68.7 68.5 GB.7 69.1 69.1; 10: 0 G9.3 69.0 G9.3 69.8 69.7 12: 0 70.8 70.1 70.8 71.2 71.0; 14: 0 73.5 72.3 73.8 74.1 73.5-18:51 87.4 83.6 89.5 86.4 87.3:

20:50 94.7 91.2 97.G 92.9 9G.1 22:50 101.6 99.1 104.9 99.7 104.G 24:50 109.3 107.4 112.9 107.1 113.2 26:50 117.7 11G.3 121.6 115.3 122.3 28:50 126.G 125.3 130.3 124.2 131.7 30:50 135.8 134.2 139.3 134.0 141.4 32:50 14G.0 143.3 149.5 145.8 151.0 34:50 158.6

.153.6 163.2

.-160.0 161.8 36:50^

171.7 164.8 177.9 175.3 173.9 38:50 187.2 178.7' 195.4 190.8-188.8 40:50 199.1 192.8 208.7 201.8 202.2 42:50 203.2 200.6 209.2 208.5 207.6-44:49 209.7 203.9 209.6

.211.3 210.4 46:49 211.4 205.4 210.3 216.0 210.8 48 49 214.4 206.5 210.6 224.2 211.0 50:49 219.5 208.7 212.4 233.3 212.0 52:49 234.4 218.5 225.8 245.4 217.8 54:49 254.5 234.7 245.9

'262.3 230.8 56:49 275.0 252.4 2G5.8 278.8 250.2 58:49 295.6 270.2 285.5 296.0 270.9 60:50 316.0 288.0 305.5 313.6 291.6

6 3

NUCLEAR POWER STATIONS WHERE THE KA0 WOOL BLANKET WRAP FIRE PROTECTION SYSTEM HAS BEEN INSTALLED J

STATION UTILITY Edwin5. Hatch Georgia Power Company Joseph M. Farley, Units 1 & 2 Alabama Power Company Grand Gulf Units 1 & 2 Mississippi Power & Light Co.

Virgil G. Sumner South Carolina Electric & Gas Co.

Susquehanna Pennsylvania Power & Light Co.

Davis Bessie Toledo - Edision Co.

Arkansas, Nuclear One Arkansas Power & Light Co.

Prarie Island Northland States Power Co.

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