ML15117A225

Summary of 940527 Meeting W/B&Wog in Rockville,Md Re Ultrasonic Testing in Lieu of Surface Exam of Reactor Vessel Nozzle Welds.List of Attendees Encl

ML15117A225
Person / Time
Site:	Davis Besse, Oconee, Arkansas Nuclear, Crystal River, 05000279, Crane
Issue date:	06/14/1994
From:	Gundrum L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9406200190
Download: ML15117A225 (37)

Text

REG~(,

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 14, 1994 Docket Nos.

50-269, 50-270, 50-287, 50-289, 50-302, 50-313 and 50-346 GROUP:

BABCOCK & WILCOX OWNERS' GROUP

SUMMARY

OF MEETING HELD ON MAY 27, 1994, TO DISCUSS ULTRASONIC TESTING IN LIEU OF SURFACE EXAMINATION OF REACTOR VESSEL NOZZLE WELDS

REFERENCES:

1.. Inspection Report 50-302/89-21 issued by the NRC on August 25, 1989

2. Letter to U.S. NRC from Duke Power Company dated November 18, 1993

3. Letter from U.S. NRC to Duke Power Company dated March 1, 1994

4. Letter to U.S. NRC from The B&W Owners' Group dated April 13, 1994 On May 27, 1994, NRC staff members met at Rockville, Maryland, with members of the Babcock & Wilcox Owners' Group (B&WOG) at a public meeting to discuss an alternative to surface examination of reactor vessel nozzle welds. A list of people attending the meeting is provided in Enclosure 1.

The B&WOG made presentations on the demonstration history, demonstration objectives, analysis and calculations to support flaw size used in the demonstration. Slides presented at the meeting, except for those designated as proprietary, are included in Enclosure 2. The slides designated as proprietary were previously submitted under affidavit on October 13, 1993.

During the late 1980's and early 1990's, relief requests were conditionally approved in safety evaluation reports (SERs) with the provision that the licensee's demonstrate the ultrasonic examination techniques and procedures applied on the inside diameter surface to detect surface connected defects on the outside diame.ter in the circumferential orientation in a laboratory test block. The defects were supposed to be cracks and not machine notches. A demonstration conducted in 1989 on a core flood nozzle with machined notches 9406200190 9406 14 PDR ADOCK 05000269 P

PDR 5(N;'C

-2 did not detect flaws in Inconel material.

In 1991, other B&W plants requested that B&WOG conduct a demonstration that could be used for all B&W plants (a generic relief request). A second demonstration conducted in 1993 on core flood nozzle and reactor coolant nozzle mockups was capable of detecting cracks larger than the maximum acceptable for the surface examination method.

In a telephone conversation on November 10, 1993, the NRC stated that the demonstration was inadequate to satisfy the condition stipulated in the SERs.

A licensee submittal (Reference 2) described the reasons for believing the 1993 demonstration fulfilled the conditions stipulated by the SERs and requested the NRC reconsider its position on the 1993 demonstration. The NRC reaffirmed its position and described its concerns in additional questions to the licensee, (Reference 3).

The response to these additional questions was submitted (Reference 4).

The subject meeting was requested to clarify what questions or concerns remained.

B&WOG stated that for the 1993 demonstration, one official set of data collected by one individual, qualified per ASME Code, was used to identify all the flaws. The procedure that was used addressed the essential variables.

The procedures that would be used for plant specific examinations would contain these same essential variables, but may have administrative changes.,

Although B&WOG did not have a precise minimum detection surface flaw length, they estimated that the indexing used in the 1993 demonstration would pick-up a 1/2-inch long flaw in at least 4 scans. This would be the same for both the reactor coolant and core flood systems.

In reviewing the fracture mechanics calculation for the core flood nozzle submitted in Reference 4, B&WOG identified at least one other plant with a 40 percent higher stress value.

In summary, the NRC is amenable to granting relief from performing surface examinations of reactor vessel nozzles to reduce radiation exposure to non destructive examination personnel.

The NRC understands that the demonstration held in 1993 was not to demonstrate an equivalency to a surface examination.

The demonstration was a capability demonstration to show that flaws located in the test block could be detected and was not intended to be a reliability demonstration. The presentation clarified that a fracture mechanics analysis (based on minimum detectable flaw size and maximum propagation rates) plus a reliability safety factor,-combined with ultrasonic testing may prove to be an acceptable alternative and meet the intent in the SER. However, the NRC would need a detailed submittal on the fracture mechanics analysis including the loadings, basis for any assumptions, and the inclusion of margins and uncertainties. The additional information needs to specify which nozzles (size, location/identification, plant) are included and state if the analyses are bounding for all plants.

At the conclusion of the meeting, the B&WOG stated they would submit additional information in four to six weeks. The NRC said this should allow sufficient time to support the first unit affected that needs the exemption by

-3 February 1995. The NRC encouraged B&WOG to work with ASME Code Committees to allow this alternative.

Original signed by Linda L. Gundrum, Acting Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees

2. Presentation Slides (nonproprietary) cc w/enclosures:

See next page DISTRIBUTION See attached page OFFICE LA:PDIII-3 APM:PDIII-3 BC:EMCB PD: PDI3 NAME Mu o

LGundr JStros e

JHann DATE_

6/9/94 6/1/94 6/10/94 6/f(94 OFFICIAL RECORD COPY FILENAME: G:\\B&WOG.MIN

cc with

Enclosures:

(Meeting Attendees)

Mr. Gene Navratil GPU Nuclear Route 441 South P.O. Box 480 Middletown, Pa 17057 Rooney Sheffield Duke Power Company McGuire Nuclear Station Hagors Ferry Road Huntersville, NC 28078 Kevin Hacker BWNT 3315 Old Forest Road Lynchburg, VA 24506 David Nix Duke Power Company Oconee Nuclear Site P. 0. Box 1439 Seneca, South Carolina 29679 Frank Walters BWNT 3315 Old Forest Road Lynchburg, VA 24506 Kenneth K. Yoon BWNT 3315 Old Forest Road Lynchburg, VA 24506 J. H. Taylor BWNT 3315 Old Forest Road Lynchburg, VA 24506

DNSTRIBUTION -

Meeting Minutes Docket Files NRC POR PD III-3.Reading File JHannon JHopkins LGundrum MRushbrook B. Grimes A. Chaffee, OEAB OGC E. Jordan JStrosnider (7-D-4)

ESullivan (7-0-4)

DNaujock (7-D-4)

LWiens (14-H-25)

LRaghavan (14-H-15)

GWest (13-E-14)

GKalman (13-H-3)

RHernan (14-C-12)

PRush, Region II KBattige (7-D-4)

ACRS (10)

OPA NRR Mailroom, PMAS, 12/G/18 S. Black, RPEB (10-A-19)

W. Dean, EDO, Region I Plants, MS 17-G-21 A. Howell, EDO, Region II Plants, MS 17-G-21 B. McCabe, EDO, Region III Plants, MS 17-G-21 J. Mitchell, EDO, Region IV Plants, MS 17-G-21 R. Cooper, Region I, DRP E. Merschoff, Region II, DRP E. Greenman, Region III, DRP A. Beach, Region IV, DRP

ENCLOSURE 1 ATTENDANCE LIST NAME AFFILIATION PHONE Gene Navratil GPU Nuclear 717-948-8716 Rodney Sleffield Duke Power Co.

704-874-4467 Kevin Hacker BWNT 804-385-3539 David Nix Duke Power Co.

803-885-3634 Frank Walters BWNT 804-385-2208 Kenneth Yoon BWNT 804-385-3280 James Taylor BWNT 804-385-2817 Ken Battige NRC/NRR 301-504-2730 Linda Gundrum NRC/NRR 301-504-1380 Garmon West, Jr.

NRC/NRR 301-504-3063 Ted Sullivan NRC/NRR 301-504-3266 Phillip Rush NRC/NRR 301-504-3743 Donald Naujock NRC/NRR 301-504-2767 Jack Strosnider NRC/NRR 301-504-1495 Len Wiens NRC/NRR 301-504-1495 Boyd Brown INEL 208-526-6048 Al Porter INEL 208-526-6048

ENCLOSURE 2 DEMONSTRATION HISTORY 1989 Demonstration Proved shear wave technique was inadequate for exams performed in 1985 for OD surface connected reflectors.

Proved longitudinal wave technique is capable of detecting OD surface connected reflectors.

1993 Demonstration

-- Proved the longitudinal wave technique is capable of detecting OD surface connected thermal fatigue flaws.

Proved the technique used provided accurate flaw sizing information.

RELIEF REQUESTS Individual B&WOG utilities have submitted relief requests to the NRC and have received SERs with the following compliance requirements:

OCONEE AND TMI-1

1.

Examine entire volume of weld and heat affected zone.

2.

Demonstrate capability to detect circumferential OD surface connected cracks, not machined notches.

CRYSTAL RIVER UNIT 3 Perform a demonstration to show the capability of the ultrasonic examination to detect and size surface flaws.

ARKANSAS NUCLEAR ONE Demonstrate the ability to detect OD surface flaws from the ID.

ISI INTERVAL END DATES FOR RELIEF REQUESTS Arkansas Nuclear One Unit 1 February 1995 Crystal River Unit 3 March 1997 Oconee Unit 1 July 1994 1, 3 Oconee Unit 2 December 1994 1,3 Oconee Unit 3 December 1994 1,3 TMI - 1 April 2001 2 1

Examination already completed 2

Two of ten examinations completed 3

Relief granted to extend subject inspection (Unit 1--10/95, Unit 2--1/96, Unit 3--5/95)

B&WOG MEETING OBJECTIVES Obtain NRC concurrence that we have successfully demonstrated compliance with NRC requests as stated in the individual utilities SERs.

B&WOG Conclusion & Summary Mockup Demonstrations verify that OD flaws of interest can be detected and sized by using the demonstrated UT techniques.

FM evaluations support the conclusion that required safety margins are maintained between minimum detectable defects and maximum expected allowable flaw size for the design conditions.

Core Flood Nozzle Safend Welds Carbon Steel Inconel SS SS SS Nozzle Butter Weld Safend Weld Piping

1. of Flaws 1

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DEMONSTRATION OBJECTIVES 1989 DEMONSTRATE THE FLAW DETECTION CAPABILITIES OF THE ULTRASONIC (UT) EXAMINATION TECHNIQUES FOR INSPECTION of PLANAR REFLECTORS OPPOSITE SURFACE FLAWS.

1993 DEMONSTRATE THE FLAW DETECTION and SIZING CAPABILITIES OF THE ULTRASONIC (UT)

EXAMINATION TECHNIQUES FOR INSPECTION of REAL OPPOSITE SURFACE FLAWS.

B&WOG UT MOCKUPS CORE FLOOD NOZZLE PIPING WELDS 1989 MOCKUP CORE FLOOD SAFE-END TO NOZZLE WELD SIMILAR (MATERIAL AND GEOMETRY) TO ALL OPERATING B&W DESIGNED PLANTS CONTAINS FOUR SETS OF PLANAR REFLECTORS (EDM NOTCHES)

DISTRIBUTED THROUGHOUT THE VARIOUS MATERIALS OF THE WELD JOINT (NOZZLE BASE MATERIAL, INCONEL BUTTERING, INCONEL WELD AND STAINLESS STEEL SAFE-END)

NOTCH SETS CONSISTED OF FOUR THROUGH-WALL SIZES: 2.3%, 5.6%, 11.3%

AND 16.9%

1993 MOCKUP CONSISTS OF A CORE FLOOD PIPE TO SAFE-END AND SAFE-END TO NOZZLE WELDS SIMILAR (MATERIAL AND GEOMETRY) TO ALL OPERATING B&W DESIGNED PLANTS

B&WOG UT MOCKUPS continued CORE FLOOD PIPE TO SAFE-END WELD CONTAINED FOUR O.D. SURFACE, THERMAL FATIGUE CRACKS DISTRIBUTED THROUGHOUT THE WELD AND BASE MATERIAL CRACK SIZES RANGE FROM 11% TO 71.8%

THROUGH-WALL CORE FLOOD SAFE-END TO NOZZLE WELD CONTAINED FOUR O.D. SURFACE, THERMAL FATIGUE CRACKS DISTRIBUTED THROUGHOUT THE VARIOUS MATERIALS OF THE WELD JOINT CRACK SIZES RANGE FROM 12.6% TO 62.9%

THROUGH-WALL

B&WOG UT MOCKUPS continued REACTOR COOLANT NOZZLE TO PIPE WELD 1993 MOCKUP CONSISTS OF A CLAD FERRITIC DESIGN SIMILAR TO ALL OPERATING B&W OPERATING PLANTS CONTAINS FIVE THERMAL FATIGUE CRACKS RANGING FROM 7.6% TO 78.7% THROUGH-WALL FLAWS DISTRIBUTED IN BOTH THE WELD AND BASE MATERIALS

DEMONSTRATION RESULTS 1989 SUCCESSFUL IN DEMONSTRATING THE DETECTABILITY OF THE UT EXAMINATION TECHNIQUE FOR SMALL (LENGTH AND THROUGH-WALL) PLANAR REFLECTORS (EDM NOTCHES) LOCATED IN THE VARIOUS MATERIALS OF THE MOCKUP DETECTED REFLECTORS AS SMALL AS 2.3%

THROUGH-WALL IN ALL THE MATERIALS OF THE WELD JOINT (NOZZLE BASE MATERIAL, INCONEL BUTTERING, INCONEL WELD AND STAINLESS STEEL SAFE-END) 1993 SUCCESSFULLY DEMONSTRATED the 100%

DETECTION OF ALL THERMAL FATIGUE FLAWS IMPLANTED IN BOTH MOCKUPS (CORE FLOOD AND REACTOR COOLANT)

ACCURATELY DEPTH SIZED ALL THERMAL FATIGUE FLAWS WITHIN A RMS ERROR OF 0.076 INCHES

INSERVICE INSPECTION FLAW ICATIO ACCEPTANCE CRITERIA IWB-3500 ACCEPTANCE BY EVALUATION IWB-3600 REPAIR/

REPLACEMENT CONTINUED OPERATION

FLAW EVALUATION o

FLAW TYPE --

EXTERNAL CIRC. FLAW ON A CYLINDER o

LOAD/STRESSES

-- DESIGN BASIS LOADS FROM STRESS REPORT HEATUP AND COOLDOWN STRESSES

-- INSPECTION INTERVAL 10 YEARS 90 CYCLES/ 10 YEARS o

MATERIAL STAINLESS STEEL daldN from Appendix C of Section XI

2.1 Weld Geometry The geometry of the two weld locations is given in Reference 5. The weld geometries are cylindrical. The pertinent dimensions for each of the weld locations are given below.

a)

For the Nozzle to Safe-end Weld Outside radius of-weld, R = 7.8125 inches Inside radius of weld, R,. = 6.125 inches ThicknesS of weld, t = 1.6875 inches b)

For the Safe-end to Pipe Weld Outside radius of weld, R = 7.125 inches Inside radius of weld, R, = 5.75 inches Thickness of weld, t = 1.375 inches

Weld (Inconel)

Clad (SS) 45'Long wave Nozzle (CS)

EDM Notch locations Safe-End (SS)

Buttering (Inconel)

Figure 1. Full Circumference Part-throughwall Flaw subjected to Axial Loading Ps6/

P, 6 1I2 I

I.. I I

I P,61l2

-R I

FLAW EVALUATION OF CORE FLOOD NOZZLE WELDS I. NOZZLE TO SAFE-END WELD MAX. ALLOWABLE FLAW a/t = 0.45

2. SAFE-END TO PIPE WELD MAX. ALLOWABLE FLAW a/t = 0.56

Core Flood Nozzle to Safe-End Flaw No.

a/i a/t%

TWB-3514 t

Max. a/tt (inches) 1

.22 12.6 10.9 1.80 2

.25 25.2 11.0 1.80 3

.28 39.5 11.1 1.80 4

.45 62.9 11.8 1.80 Core Flood Safe-End to Pipe 7

.17 22.0 11.1 1.10 8

.25 38.6 11.5 1.10 9

.29 71.8 11.6 1.10 10

.16

11. 0 11.1 1.10 Reactor Coolant Outlet Nozzle to Pipe 1

.25 7.6 11.7 3.0 2

.50 78.7 13.2 3.0 3

.27 16.3 12.3 3.0 4

.45 37.1 13.2 3.0 5

.28 10.9 12.6 3.0

ALLOWABLE FLAW SIZE 100 90 o-SAFE-END TO PIPE r1 NOZZLE TO SAFE-END WELD 60 50 ALLOWABLE LIMIT BY EVALUATION 30 a DETECTABILITY 20I DEMONSTRATION 10 ACCEPTANCE CRITERIA 0

Toledo Edison Company Davis-Besse Nuclear Power Station Unit No. 1 cc:

Mary E. O'Reilly Attorney General Centerior Energy Corporation Department of Attorney General 300 Madison Avenue 30 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43216 Mr. William T. O'Connor, Jr.

Mr. James W. Harris, Director Manager - Regulatory Affairs Division of Power Generation Toledo Edison Company Ohio Department of Industrial Davis-Besse Nuclear Power Station Regulations 5501 North State - Route 2 P. 0. Box 825 Oak Harbor, Ohio 43449 Columbus, Ohio 43216 Gerald Charnoff, Esq.

Ohio Environmental Protection Agency Shaw, Pittman, Potts DERR--Compliance Unit and Trowbridge ATTN: Zack A. Clayton 2300 N Street, N. W.

P. 0. Box 1049 Washington, D. C. 20037 Columbus, Ohio 43266-0149 Regional Administrator, Region III State of Ohio U. S. Nuclear Regulatory Commission Public Utilities Commission 801 Warrenville Road 180 East Broad Street Lisle, Illinois 60532-4351 Columbus, Ohio 43266-0573 Mr. Robert B. Borsum Mr. James R. Williams Babcock & Wilcox State Liaison to the NRC Nuclear Power Generation Division Adjutant General's Department 1700 Rockville Pike, Suite 525 Office of Emergency Management Rockville, Maryland 20852 Agency 2825 West Granville Road Resident Inspector Columbus, Ohio 43235-2712 U. S. Nuclear Regulatory Commission 5503 N. State Route 2 Mr. Donald C. Shelton Oak Harbor, Ohio 43449 Vice President, Nuclear-Davis-Besse Centerior Service Company Mr. John K. Wood, Plant Manager do Toledo Edison Company Toledo Edison Company 300 Madison Avenue Davis-Besse Nuclear Power Station Toledo, Ohio 43652 5501 North'State Route 2 Oak Harbor, Ohio 43449 Robert E. Owen, Chief Bureau of Radiological Health Services Ohio Department of Health Post Office Box 118 Columbus, Ohio 43266-0118

Entergy Operations, Inc.

Arkansas Nuclear One, Unit 1 cc:

Mr. Harry W. Keiser, Executive Vice Mr. Jerrold G. Dewease President & Chief Operating Officer Vice President, Operations Support Entergy Operations, Inc.

Entergy Operations, Inc.

P. 0. Box 31995 P. 0. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Charles B. Brinkman, Manager Mr. Robert B. McGehee Washington Nuclear Operations Wise, Carter, Child & Caraway ABB Combustion Engineering P. 0. Box 651 Nuclear Power Jackson, Mississippi 39286 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Admiral Kinnaird R. McKee, USN (Ret) 214 South Morris Street Mr. Nicholas S. Reynolds Oxford, Maryland 21654 Winston & Strawn 1400 L Street, N.W.

Washington, D.C. 20005-3502 Mr. Robert B. Borsum.

Licensing Representative B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Rockville, Maryland 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 310 London, Arkansas 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable C. Doug Luningham County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72205-3867

Duke Power Company Oconee Nuclear Station cc:

A. V. Carr, Esquire Mr. Steve Benesole Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.

Mr. Marvin Sinkule, Chief Washington, DC 20005 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. G. A. Copp Licensing -

ECO50 Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission 526 South Church Street Route 2, Box 610 Charlotte, North Carolina 28242-0001 Seneca, South Carolina 29678 Mr. J. W. Hampton Regional Administrator, Region II Vice President, Oconee Site U. S. Nuclear Regulatory Commission Duke Power Company 101 Marietta Street, NW. Suite 2900 P. 0. Box 1439 Atlanta, Georgia 30323 Seneca, South Carolina 29679 Max Batavia, Chief Dayne H. Brown, Director Bureau of Radiological Health Division of Radiation Protection South Carolina Department of Health North Carolina Department of and Environmental Control Environmental Health and 2600 Bull Street Natural Resources Columbia, South Carolina 29201 P.0 Box 27687 Raleigh, North Carolina 27611-7687 County Supervisor of Oconee County WalhallaS, South Carolina 29621

Crystal River Unit No.3 Florida Power Corporation Generating Plant cc:

Mr. Gerald A. Williams Mr. Joe Myers, Director Corporate Counsel Div. of Emergency Preparedness Florida Power Corporation Department of Community Affairs MAC-A5A 2740 Centerview Drive P. 0. Box 14042 Tallahassee, Florida 32399-2100 St. Petersburg, Florida 33733 Mr. Bruce J. Hickle, Director Chairman Nuclear Plant Operations (NA2C)

Board of County Commissioners Florida Power Corporation Citrus County Crystal River Energy Complex 110 North Apopka Avenue 15760 W. Power Line Street Inverness, Florida 32650 Crystal River, Florida 34428-6708 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director B&W Nuclear Technologies Nuclear Operations Site Support (NA21) 1700 Rockville Pike, Suite 525 Florida Power Corporation Rockville, Maryland 20852 Crystal River Energy Complex 15760 W Power Line Street Crystal River, Florida 34428-6708 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Senior Resident Inspector 101 Marietta Street N.W., Suite 2900 Crystal River Unit 3 Atlanta, Georgia 30323 U.S. Nuclear Regulatory Commi ssion Mr. Bill Passetti 6745 N. Tallahassee Road Office of Radiation Control Crystal River, Florida 34428 Department of Health and Rehabilitative Services Mr. Gary Boldt 1317 Winewood Blvd.

Vice President Nuclear Tallahassee, Florida 32399-0700 Production (SA2C)

Florida Power Corporation Attorney General Crystal River Energy Complex Department of Legal Affairs 15760 W Power Line Street The Capitol Crystal River, Florida 34428-6708 Tallahaseee, Florida 32304 Mr. Percy M. Beard, Jr.

Sr. Vice President Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing (NA2I)

Crystal River Energy Complex 15760 W Power Line Street Crystal River, Florida 34428-6708

Three Mile Island Nuclear Station, Unit No. 1 cc:

Michael Ross Michele G. Evans O&M Director, TMI-1 Senior Resident Inspector (TMI-1)

GPU Nuclear Corporation U.S. Nuclear Regulatory Commission Post Office Box 480 Post Office Box 311 Middletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 John C. Fornicola Regional Administrator, Region I Director, Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs 475 Allendale Road GPU Nuclear Corporation King of Prussia, Pennsylvania 19406 100 Interpace Parkway Parsippany, New Jersey 07054 Robert B. Borsum Jack S. Wetmore B&W Nuclear Technologies TMI Licensing Manager Suite 525 GPU Nuclear Corporation 1700 Rockville.Pike Post Office Box 480 Rockville, Maryland 20852 Middletown, Pennsylvania 17057 Ernest L. Blake, Jr., Esquire William Dornsife, Acting Director Shaw, Pittman, Potts & Trowbridge Bureau of Radiation Protection 2300 N Street, NW.

Washingtn, DCW003 Pennsylvania Department of Washington,Environmental Resources Post Office Box 2063 Chairman Board of County Commissioners of Dauphin County Mr. T. Gary Broughton, Vice President Dauphin County Courthouse and Director -

TMI-1 Harrisburg, Pennsylvania 17120 GPU Nuclear Corporation Post Office Box 480 Chairman Middletown, Pennsylvania 17057 Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, Pennsylvania 17057