ML20054D288

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Summary of 820224-25 Meetings W/Util & Eg&G in Jenkinsville,Sc Re Inservice Test Program for Pumps & Valves.List of Attendees Encl
ML20054D288
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/16/1982
From: Kane W
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8204220536
Download: ML20054D288 (19)


Text

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MAR 161982 Docket No.: 50-39S APPLIC A!!T: South Carolina Electric & Gas Company FACILITY:

Virgil C. Sunner Nuclear Station, Unit 1

SUBJECT:

SU! MARY OF FEBRUARY 24-25 t!EETIt!G REGARDIllG I!! SERVICE TEST PROGRA!1 FOR PUf4PS AtlD VALVES General Representatives of the staff and its consultant (EG&G Idaho) not with the applicant and its consultants to discuss the inservice test progran (IST) for pumps and valves. The neeting was held at the Virgil C. Sunner Nuclear Station in Jenkinsville, S. C.

A list of those persons who attended the necting is included in Enclosure A.

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Purpose The purpose of the reeting was to review responses to those questions attached to our neeting notice dated February 4,1982, H. Kane to B. J. Youngblood.

l Discussion The applicant's responses to the meeting questions are contained in Enclosure B.

The significant observations fron the neeting are discussed below:

1.

The applicant feels that passive containment isolation valves, those that do not change position to perform their containment isolation function, should not be included in the IST progran since their operability is not important to performing their safety function. They feel since these valves are leak tested to the Appendix J requirenents, this would be a duplication of testing requirements if they are included in the IST progran. We informed the applicant that it is the staff's position that

'o all containment isolation valves that are leak rate tested per Appendix o J are required to be included in the IST program as Category A or A/C valvesf
  • r 2.

The applicant utilizes small (3/4 inch) check valves, 8703A A B, to provide thernal overpressure protection for the sections of piping between valves 8701A & B and 8792A & B, RHR suction from RCS hot leg.

The applicant does not consider these valves to perform a safety l

function; they are for equipnent protection only, and therefore will not include them in the IST progran. This iten is still open.

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0204220536 820316 l

c PDR ADOCK 05000395-PDR me roe. C FFICIAL RECORD COPY usanum-m-oeo

m South Carolina Electric & Gas MAR 161982 Company 3.

The applicant feels that passive valves 8701A & B and 8702A & B, the RHR systen suction from the RCS hot legs isolation valves, should not be included in the IST program since operability of these valves is not important to perforning their safety function. They agree that these valves do perforn a pressure isolation function and do perfom leak rate testing per Technical Specifications, but feel including these valves in the IST progran would be a dupitcation of testing requirenents. We infomed the utility that it is the staff's position that all identified RCS pressure isolation valves that are required to be leak rate tested, will be included in the IST progran as Category A or A/C valves.

4.

The applicant has proposed a test frequency of alternate refueling outages for the reactor butiding spray check valves 3009A & B.

The applicant has recognized that the only practical nethod of full stroke exercising these valves is by disassembly an f nanually noving the valve discs. However, they contend that perfoming this test on one valve per ref::aling outage is sufficient to denonstrate operabi-li ty. lie stated the staff position is that each valve must be exercised at an interval not to exceed each refueling outage. The applicant will be providing nore infomation based on radiation levels, nan /ren exposures, etc. to try to justify their identified testing frequency.

Origina1 signed by.,3 William Kane II. F. Kane, Project Manager Licensing Branch flo.1 Division of Licensing

Enclosures:

As stated cc w/encls.:

See next page Y

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Mr. T. C. Nichols, Jr.

Vice President & Group Executive Nuclear Operations South Carolina Electric & Gas Company Post Office Box 764 Columbia, South Carolina 29218 cc: Mr. Henry Cyrus Senior Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 J. B. Knotts, Jr., Esq.

Debevoise & Liberman 1200 17th Street, N. W.

Washington, D. C.

20036 Mr. Mark B. Whitaker, Jr.

Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company Post Office 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1, Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o U..S. NRC Route 1, Box 64 Jenkinsville, South Carolina 29065 Mr. James P. O'Reilly U. S. NRC, Region II 101 Marietta Street Suite 3100 Atlanta, Georgia 30303 o

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ENCLOSURE A LIST OF ATTENDEES

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HRC Staff SCE&G Staff J. Skolds H. Clark E. Girard A. Paglia R. Clary S. Smith EG8G Idaho, Inc.

J. Turkett L. Collier H. Rockhold T. McAlister W. Hubble L. Storz S. Buske G. Soult R. Lyon D. Conrad NUS Corporation J. Monroe f

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ENCLOSURE B A.

General Questions 1.

The "POS IND" column indicates the valve has remote position indica-tion. The valve position indicator verification per IWV-3300 is covered by tha applicable surveillance test procedures.

2.

The f ail safe test is performed when the applicable surveillance test procedure requires it.

B.

Reactor Coolant System 1.

Valve 8046 will be verified closed quarterly by shutting a manual valve upstream and monitoring the pressure to determine valve closure.

2.

The power operated relief valves and the block valves will be included in the IST program as category B valves and full stroke exercised and stroke timed quarterly. No relief required.

3.

The P&ID that shows the reactor vessel head vents was provided and these valves were identified as pressure boundary isolation valves and tested per the code.

C.

Chemical and Volume Control System 1.

Check valve 8381 will be tested during cold shutdowns. The applicable relief request will be revised by the utility to include the specific consequences of securing letdown and charging flow during power operation.

2.

Valves 8153, 8154, and 8145 will be deleted from the IST program.

These valves do not perform any safety function.

3.

The listed valves will be deleted from the IST program. These valves do not perform any safety function.

)

4 The utility does not consider 8117 to perform a safety function and will not include it in the IST program. This valve is leak rate j

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tested per Appendix J.

Open item for NRC to transmit to the utility the NRC's position that all Appendix J leak rate tested valves will be included in the IST program as category A or A/C valves.

5.

Valves 8100 and 8112 will not be classified as passive valves. These valves will be full stroke exercised quarterly.

No relief requireo.

6.

The utility does not consider 8103 to perform a safety function and will not include it in the IST program. This valve is leak rate tested per Appendix J.

Open item, see item C.4.

7.

The utility does not consider valves 8368 A, B, & C and 8102 A, 8, & C to perform a safety function and will not include them in the IST program. These valves are leak rate tested per Appendix J.

Open item, see item C.4.

8.

Check valves 8481 A, B, & C will be full flow exercised during refuel-ing outages and will be partial flow exercised quarterly. The utility will provide a relief request with sufficient technical justification for these testing frequencies.

9.

The relief request for valves LCV-ll5 C & E will be. modified to pro-vide sufficient technical justification for not full stroke exercising these valves during power operation. These valves will be full stroke exercised during cold shutdowns.

10.

Valve 8104 will be full stroke exercised quarterly. The line can be isolated so highly concentrated boric acid will not be introduced into the normal charging path. Valve 8442 cannot be full or partial flow exercised during power operation since this would introduce highly concentrated boric acid into the normal charging path resulting in a power transient and could result in plant shutdown. This valve will be full flow exercised during cold shutdown.

11. Valves LCV-460 and 459 will be deleted from the IST program. These valves do not perform a safety function.

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12. Valve 8117 is discussed. in item C.4
13. The utility will provide a detailed technical justification for not full or partial stroke exercising valves 8107 and 8108 during power operation.

These valves will

  • e full stroke exercised during colo o

' shutdowns.

14 Valve 8130 A & B, 8131 A & B, 8132 A & B, and 8133 A & B will not be in the IST program since they do not perform a safety function.

15. Valve 8440 will remain in the IST program and will be full flow exercised quarterl.v.

D.

Residual Heat Removal System 1.

Valves 8716 A & B will be full flow exercised quarterly.

2.

Valves 603 A & B (RHR heat exchanger outlets) and 605 A & B (RHR heat exchanger bypasses) are passive valves which require no testing.

I Therefore, they will not be included in the IST program.

1 The utility does not consider '8703 A & B to perform a safety function and will not include them in the IST program. These valves are leak

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rate tested per technical specifications (pressure beundary isolation valves). Open iten for NRC to determine if they should be included in the IST program.

t 3.

The utility does not consider 8701 A & B and 8702 A & B to perform a j

safety function and will not include them in the IST progran. These valves are leak rate tested per technical specifications (pressure boundary ' isolation valves). Open item for NRC to transmit to the

-utility the NRC's position that all pressure boundary isolation valves that are leak rate tested will be included,in the IST program as cate-gory A or A/C valves.

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Valves 8706 A & B will be included in the IST program as category B valves and full stroke exercised quarterly.

No relief required.

E.

Safety Infection System

. i 1.

Valves 8998 A, 8, & C will be full flow exercised during cold shut-downs. The relief request for these valves will be revised to provide the specific technical justification for exercising at this frequency.

2.

Valves 8997 A, B, & C cannot be full or partial flow exercised during power operation since establishing flow through these valves would place unnecessary thermal stresses 09 the safety injection piping.

During cold shutdowns, establishing flow through these valves could result in solidification of highly concentrated boric acid from the BIT in the non heat traced piping.

These valves will be full flow exercised during refueling outages wheg system flushing can be per-fo rmed.

3.

Check valves 8995 A, B, & C cannot be full or partial flow exercised during power operation since establishing flow through these valves would place unnecessary thermal stresses on the safety injection pip-ing. Establishing flow through these valves during cold shutdown could result in a low temperature overpressurization of the reactor coolant system. These valves will be full flow exercised during refueling outages.

4.

Check valves 8988 A & B will be full flow exercised during cold shut-downs. Relief request " alternative test" will be changed to reflect the " cold shutdown" frequency of testing.

1 5.

Check valves 8993 A, B, & C cannot be full or partial flow exercised during power operation since establishing flow through these valves would place unnecessary thermal stresses on' the safety injection pip-ing. Check valves 8993 A & B will be full flow exercised during cold shutdowns. Check valve 8993 C cannot be* full or partial flow exercised 4

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during cold shutdowns since exercising could redit 'in a low tempera-ture overpressurization of the reactor coolant system. 8993 C will be full flow exercised during refuelfr!,g futages.

6.

Check valves 8990' A, B, & C and c992 A, 8, &.C cannot be full cr partial flow exercised during power operation since establishing flow through these valves would place unnecessary thermal stresses on the safety injection piping.

Establishingflow$hroughthesevalvesdur-ing cold shutd0wn could result in a low temper'athr'e overpressurizaticn of the reactor coolant system. These valve's will be full flow exercised during refueling outages.

7.

Valves 8803. A & B will be full stroke exercised during cold shutdown.

The associated relief request will be revised by the utility to pro-vide sufficient technical justification 'for this exercising frequency.

Valves 8801 A & B will be full stroke 'e.xercised during refueling out-ages. A relief request with sufficie'nt' technical justification for this exercising frequency will be provided by the utility.

8.

The utility does not consider check valves 8940 A & B to perform a safety function and will not include these valves in the IST program unless directed to do so by the NRC. Open item for NRC to determine if these valves perform a safety fun,ction.

The utility will rewhite,the relief request for check valves 8948 A, 9.

8, & C and 8956 A, B, &,C to indicate no full or partial stroke exer-cising can be accomplished during power operation or cold shutdown.

Additionally, these valves cannot be full stroke exercised during refueling outages. The utility will revise the applicable relief a

  • ]

request to' provide sufficient technical justification for not perform-i-

ing the required exercising. These valves are leak rate tested per s,

technical specifications (pressure boundary isolation valves). These i.< valves will be categorized A/C in the IST program.

Included in the 1

relief request will be alternate. tests considered for full stroke exercising and why these alternate tests cannot be utilized.

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10. The relief request for valves 8808 A, B, & C will be modified to indicate these valves cannot be shut during power operation because of technical specification limitations.

11.

Check valves 8947 and 8861 can only be verified closed (their safety related position) by leak. rate testing. These valves will be leak rate tested per Appendix J during refueling outages.

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12. The utility will full flow exercise check valves 8974 A & B and 8973 A, B, & C during cold' shutdowns.- Check valves 8974 A & B are leak rate tested in accordance with Appendix J.

Check valves 8973 A, B, & C are leak r:ta tested in accorda.ca with technical specificaticas (pressure boundary isolation valves). Closure is verified during the applicable leak rate testing.

13.

Check valves 8958 A & B are full flow exercised quarterly.

14. There are no system interlocks that prevent opening valves 8811 A & B and 8812 A & B during power operation. These valves will be full stroke exercised quarterly.
15. Check valve 8926 cannot be full or partial flow exercised during power operation since this would require injection of highly con'centrated i

boric acid from the RWST into the RCS causing a power transient and could result in plant shutdown. During cold shutdowns this valve cannot be exercised since a low temperature overpressurization of the RCS could result. This valve-will be full flow exercised during refueling outages.

16. Valves 8884 and 8886 will be included in the IST program.

.17.

Valves 8884, 8885 and 8886 cannot be full or partial stroke exercised during power operatinn since opening those ' valves would establish flow into the RCS resulting in unnecessary thermal transients to the safety l

injection piping. -These valves will be full stroke exercised during cold shutdowns.

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18. Valves 8889 and 8888 A & B will be included in the IST program. The utility will supply a relief request providing sufficient technical justification for exercising these valves during cold shutdowns.

Valves 8887 A & 8 will not be included in the IST program as tney are used for maintenance only.

19. Valves 8812 A & B are not Appendix J ieak rate, tested and do not per-form a ccntainment isolation function. These valves will be categor-ized B in the IST program.

20.

Val /cs 3009 A & 3 will be f acludsd in the IST program and categor-ized B.

Closure of these valves during power operation places the plant in a limiting condition for operation and failure of the valves to reopen requires plant shutdown. Therefore, these valves will be full stroke exercised during cold shutdowns.

F.

Main Steam System 1.

The main steam line isolation valves, 2801 A, B, & C, will be partial stroke exercised quarterly during power operations and full stroke exercised during cold shutdowns.

2.

The utility will insure that check valves 2876 A & B are full flow exercised at least quarterly during the turbine driven emergency feed-water pump tes ting.

3.

Valve 2813 shuts to preclude loss of steam during emergency feedwater pump operation. This valve will remain in the IST program as a cate-gory B valve. No relief required.

4.

Relief valves 2806 K, L, M, N, & P will be included in the IST program as category C relief valves and tested per 'the code.

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5.

Valves 2877 A & B and 2843 A, B, & C are for equipment protection /

operating convenience.

These valves do not receive any safety signal and will not be included in the IST program.

G.

Feedwater System 1.

Valves 1633 A, B, & C are not leak rate tested per Appendix J and will-be categorized B/C. These valves are tested per the code and do not require relief.

2.

Valves 1611 A, B, & C cannot be partial stroke exercised because of their control circuit design. These valves will be full stroke exer-cised during cold shutdowns.

3.

Valves 1680 A, B, & C and 1684 A, B, & C will be deleted from the IST program since these valves do not perform any safety function.

4.

Valves 1678 A, B, & C will be deleted from the IST program since these valves do not perform any safety function.

H.

Emergency Feedwater System 1.

Check valves 1016 and 1020 A, B, & C will be full ficw exercised dur-

.ing the process of going to cold shutdown.

2.

Check valves 1013 A & B, and 1014 'will be partial flow exerciseo quarterly during power operations and full flow exercised during cold _

shutdowns. The utility will supply a relief request -providing suf-ficient technical justification for these frequencies.

3.

Full or partial flow exercising of check valves 1034-A & B and 1022 A

& B could introduce service water into the steam generators. Open item for utility to determine a method and. frequency for full stroke exercising these valves.

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4.

Valves 1001 A & B,1002,1008, and 1037 A & B cannot be exercised during power operation since service water could be introduced into the emergency feedwater piping. These valves will be full strcke exercised during cold shutdowns.

5.

Check valves 1023 A & B,1024, and 1027 will be included in the IST program and categorized C.

These V:lves will be tested per the ASME code, no relief required.

6.

Valves 1009 A, B, & C will be categorized C and full stroke exercised quarterly (with torque wrench).

No relief required.

7.

Check valves 1019 A, B, & C and 1020 A, B, & C will be included in the IST program as category C valves.

Exercising these valves during power operation would result in unnecessary thermal stresses to the steam generator and associated piping. These valves will be full flow exercised during cold shutdowns.

I.

Service Water System 1.

The safety related position of check valves 3130 A & B and 3135 A & B is open and these valves are full flow exercised quarterly.

No relief required.

2.

Check valves 3137 A & B will be full flow exercised quarterly. No relief required.

3.

Valves 3103 A & B will be full stroke exercised quarterly.

No relief required.

4.

Check valves 3120 A & B will not be included in the IST program.

These valves are for equipment protection only.

5.

Valve 3168 will be deleted from the IST program as the valve performs no safety function.

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6.

Valves 3107 A & 8 will be full stroke exercised during cold shut-down s. The utility will provide a revised relief request providing sufficient technical justification for this testing frequency.

ml.

Station Service Air System 1.

The utility does not consider check valve 2913 to perfor.n a safety function and will not include it in the IST program.

This valve is leak rate tested per Appendix J.

Open item, see item C.4.

2.

The utility does not consider valve 2912 to perform a safety function and. ill not includa it in the IST program.

This valve is leak rate tested per Appendix J.

Open item, see item C.4.

K.

Instrument Air System 1.

Valves 2662 A & B will be full stroke exercised quarterly.

No relief required.

Valves 2660 and 2661 cannot be exercised during power operations since this would isolate instrument air to containment. These valves will be full stroke exercised during cold shutdowns.

L.

Nitrogen Blanketing System 1.

The utility does not consider check valve 6588 to perform a safety function and will not include it in the I5T program. This valve is leak rate tested per Appendix J.

Open item, see item C.4.

2.

The utility does not consider valve 6587 to perform a safety function and will not include it in the IST program. This valve is leak rate tested per Appendix J.

Open iten, see item C.4.

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M.

Diesel Generator Fuel Oil System 1.

Check valves 970 A & B, 971 A & D, and 972 A & B will be full flow exercised quarterly.

No relief required.

N.

Component Cooling System 1.

Valves 9627 A & B will be deleted from the IST program since these valves perform no safety function.

Open iten for NRC to determine if these valves do perform no safety function.

2.

Valve 9505 will be categorized A in the IST progrtm.

No relief required.

3.

Check valve 9689 is a normally shut passive valve and will not be included in the IST program. This valve is leak rate tested per Appendix J.

Open item, see item C.4.

4.

Check valve 9570 cannot be exercised shut during power operation or cold shutdown since this would require isolating cooling water to the reactor coolant pump bearing coolers and the RCDT heat exchanger and isolating flow could result in equipment damage. This valve wil be exercised shut during refueling outages.

5.

Check valves 9632 and 9633 perform no safety function and will be deleted from the IST program.

6.

Valves 9625 and 9626 perform no safety function and will be deleted from the IST program.

7.

Valves 9600, 9605, 9606, and 9568 are not passive valves and will be full stroke exercised during refueling outages for the same reasons as given in item N.4 Check valve 9689 is discussed in item N.3.

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8.

Check valve 9602 will be exercised shut during refueling outages for the same reasons as given in item N.4 9.

The listed valves provide no safety function, therefore they will not-be included in the IST program.

P.

Reactor Building Spray System 1.

Check valves 3009 A & B are physically located in high radiation areas.

Open item for utility to provide approximate time required and expected radiation doses for performing the valve disassembly required for verificatien of valve operability. This inform:ticn will be based on currently available cata and best estimates.

2.

Valves 3005 A & B will remain in the IST program as category 8, no relief required.

(These valves are not leak rate tested per Appendix J.)

3.

Check valves 3013 A & B cannot be full flow exercised since this would require introduction of highly corrosive sodium hydroxide inte the reactor building spray system. These valves will be partial flow exercised quarterly utilizing the nearby drain line connections.

Open item for utility to determine a method and frequency for full stroke-exercising these valves.

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4 4.

Valves 3002 A & B cannot be full stroke exercised during power opera -

tion since this would require isolation of the sodium hydroxide tank.

These valves will be full stroke exercised during cold shutdown when I-

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the tank can be isolated and downstream piping can be flushed.

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Q.

Nuclear Sampling System 1.

The utility does not' consider. valves 9386 A, 8, & C to perform a ' safety

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function and will not include these valves in the IST program. These valves are leak rate tested per Appendix J.

Open item, see, item C.4.

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R.

Chilled Water System 1.

Valves 6410 A & B, 6489 A & B, 6387 A & B, and 6388 A & B will be included in the IST program as category C valves.

Open item fer utility to determine a method and frequency for verifying valve closure (their safety related position).

S.

Post Accident Hydrogen Removal System 1.

Valves 6056, 6057, 6066, and 6067 will be full stroke exercised quarterly.

No relief required.

2.

Valves 6063, 6062, 6068, and 6064 perform no safety function and will not be included in the IST program.

T.

Ventilation System 1.

Valves 0001 A & B and 0002 A & B cannot be exercised during power operation since the plants technical specification require these valves to be closed. Open item for utility to determine a method and frequency for full stroke exercising these valves.

U.

Fire Protection System 1.

P&ID 302-231 was provided for our review at the working meeting.

Valve 6799 is a passive check valve therefore exercising is not required. However, this valve is leak rate tested per Appendix J.

The utility does not consider this valve to perform a safety function and will delete this valve from the IST program.

Open item, see item C.4.

V.

Miscellaneous Syste'ms l

1.

Valve 2865 will be removed from the IST program.

This valve is tested as an integral part of the emergency feedwater pump / turbine.

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l 2.

Valves 524, 525, 541, and 547 do not perform a safety function and will be deleted from the IST program.

3.

Valves -6461 A, 8, & C will be included in.the IST program as cate-gory C valves. :These valves will be full flow exercised quarterly.

No relief required.

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4.

Response to valve 6588 is incl,uded in item L.l.

Response to valve 2913 i

is included in item J.l.

t 5.

P&IO 302-852 was provided for our review at the working meeting.

f The utility does not consider valves 7541 and 7544 to perform a safety function and will not include them in the IST program. These valves j

are leak rate tested per Appendix J.

Open item, see item C.4.

6.

System code "AC" will be included in the IST program list of systems.

j AC--CRDM Cooling System.

7.

P&ID 302-772 was provided for our review at the working meeting.

No further comments.

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8.

P&ID 302-613 was provided for our review at the working meeting.

No

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j further comments.

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F 14-1

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r PUMP TESTING PROGRAM A.

General Questions 1.

Section 4.4.2 of the IST program was prcvided for our review at the working meeting, 2.

Section 6.0 of the IST program was provided for our review at. the working meeting.

3.

Service water pump parameters are taken as follows:

inlet pressure calculated from the water level of the service water pond vibration taken (horizontally only) from the pump shaft between the pump and coupling (utiliziag IRD-360) flow from individual flowmeters installed downstream of each cooled component and then these are summed.

4.

The component cooling pumps have two fixed speeds, therefore the pump speed is not required to be measured.

5.

All required parameters for the HVAC chilled water pumps are measured /-

observed and recorded per code.

6.

The Boric Acid Transfer pump parameters are taken as follows:

inlet pressure height of boric acid in storage tank bearing temperature not required since bearings are cooled by punped liquid vibration measured on the punp supports.

7.

Surveillance test procedures provided for our review at the working meeting.

No further comments.

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MEETING

SUMMARY

DISTRIBUTION

" Dockst File G. Lear fiRC PDR W. Johnston MAR 161902 Local PDR S. Pawlicki n,

TIC /ftSIC/ Tera V. Benaroya

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s Z. Rosztoczy LB#1 Reading W. Haass 2

t H. Denton/E. Case D. Muller j'

e '~ '~n P M? r ;/ O22% M R. Ballard 0

7"b D. Eisenhut/M. Jambor W. Regan p I:

f/vD RZ Ma ttson

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B. J. Youngblood

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M A. Schwencer F. Congel 7 --

1 F. Miraglia

0. Parr

' / g/

l J. Miller F. Rosa l

G. Lainas W. Butler R. Vollmer J. P. Knight R. Houston R. Bosnak F. Schauer L. Rubenstein R. E. Jackson T. Speis Project Manager W. Kane M. Srinivasan Attorney, OELD J. Stolz M. Rushbrook S. Hanauer OIE (3)

W. Gammill ACRS (16)

W. Minners F. $cnroeder E. Adensam D. Skovholt M. Ernst NRC

Participants:

L. Hulma'n efingr J. Skolds, RI "I*I E. Girard G. Knighton A. Thadani J, Kramer D. Ziemann bcc:

Applicant & Service List e

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