ML20070M679

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Forwards Proposed Amend on Unidentified Leakage,As Requested in ALAB-702.Svc List Encl
ML20070M679
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 01/21/1983
From: Silberg J
ALLEGHENY ELECTRIC COOPERATIVE, INC., PENNSYLVANIA POWER & LIGHT CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Buck J, Eilperin S, Moore T
NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
ALAB-702, NUDOCS 8301250296
Download: ML20070M679 (1)
v • d • e


Text

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SHAW, PITTMAN, PoTTs & TROWBRIDGE A PAnTNERSMsp CF PeoFESSloNAL CORPORATIONS 1800 M STR E ET, N. W.

WASHINGTON, D. C. 2OO3e 00LKETED Tc o rCo., c.

CWC taoai saa-soes & saa-irse January 21, 1983 -

TELEX so ase3 ISMAWLAW WSMI m3 JZ 24 NOM 0 cA.< = . A-LA -

TELEPMoNC

.J AY E. SIL BERO P.C. taoatsaa4oe3 Thomas S. Moore, Esquire Administrative Judge Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. John H. Buck Administrative Judge Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Stephen F. Eilperin, Esquire Administrative Judge Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission l Washington, D.C. 20555 l

Re: Pennsylvania Power & Light Company and Allegheny Electric Cooperative, Inc. (Susquehanna Steam Electric Station, Units 1 and 2) Docket Nos. 50-387 and 50-388 l Gentlemen:

In ALAB-702, the Appeal Board requested that Applicants. inform the Board when Applicants file their proposed amendment on uniden-tified leakage. Enclosed is a copy of Applicants' filing which,,__- '

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includes as Item 5 the proposed amendment. -

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5 l

l Very truly yours, 1

SHAW, PITTMAN, POTTSJ& TROWBRIDGE i f/

BY: -

u / (,

JAY E. SILBERG, Pg Counsel' f r Applicants Enclosure i cc: Service List JES: lam ~

l f' r3012502% 830121

,O PDR ADOCK 05000387 PDR h

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my b 'gG Pennsylvania Power & Light Company Two North Ninth Street e Allentown, PA 10101

  • 215 1 770 5151 Norrnan W. Curtis

%ce President-Engineering & Construction-Nuclear

. 215 / 770-5381 Mr. A. Schwencer, Chief '

Licensing Branen No. 2 U.S. Nuclear Regulatory Commission '

1 Washington, D.C. 20555 i SUSQUEHANNA STEAM ELECTRIC ST.dION PROPOSED AMENDMENT 15 TO LICENSE NPF-14 ER 100450 FILE 841-8 PLA-1430 Docket No. 50-387

Dear Mr. Schwencer:

The purpose of this letter is to present several proposed changes to Appendi:c "A" to License No. NPF-14, the Susquehanna SES Unit 1 Technical Specifications.

ITDi 1: Specification 6.5.2.8.e.

Proposed Change: Revise per Attachment 1 Justification for Change: Generic Letter No. 82-17 ITDI 2: Specification 6.5.2.8.f.

Proposed Change: Revise per Attachment 2 Justification for Change: Generic Letter 82-23 ITEM 3: Specification 6.9.1.6 Proposed Change: Revise per Attachment 3 Justification for Change: During the reorgani::sti.on of the NRC, the Management Information Branch became the correct addressee for Monthly Operating Reports.

ITEM 4: Specification 3.10.5 Proposed Change: Revise per attachment 4A i

%7 CM S y.

l

i Pega 2 SSES PLA-1k30 ER 100450 File 841 Mr. A. Schwencer, Chief

~

Justification for Change: Special Test Exception 3.10.5 was wricten in

. order to provide access to pri=ary containment during startup testing. The Susquehanna SES Startup Test Program is currently projected to be complete in late March or early April, 1983.

10CFR50.44 (Attach =ent 43) requires SSES to have an inerted at=osphere 6 =onths after initial criticality - March 10, 1983. An exe=ption is requested in order to allow SSES to finish startup testing before having to inert primary containment, based on the belief that there is no safety impact associated with the 6-month restriction as long as SSES is held to Specification 3.10.5.

ITEM 5: Specification 3.4.3.2 1

Proposed Change: Revise per Attachments SA and 5B Juatification for Change: This change is consistent with the te==it=ents made in PPSL's response (dated November 2, 1982) to the sua sponte question raised by the Atomic Safety and Licensing Appeal Board (Order dated October 26, 1982).

ITEM 6: Specification 3.9.1 Proposed Change: Revise per Attachment 6 ,

Justification for Change: The proposed change clarifies the intent of the "1#" footnote. The LCO requires the mode switch to be locked in the Shutdown or Refuel position. The footnote permits movement .to alternative positions when testing of switch functions is being perfor=ed. Moving the footnote to the Applicability state =ent enhances operator awareness of this provision.

ITEM 7: Specification 4.8.4.1.a.2.

Proposed Change: Revise per Attachment 7 Justification for Change: The existing requirement requires sample testing (10~ mini =um) of the protective fuses for primary containment penetration circuits on a rotational basis. The purpose of this requirement is to assure circuit isolation on fault conditions to prevent heating of the penetration ceal and possible subsequent damage. This mode of protection requires that the fuse open when currents in excess of the fuse rating occur. Also of concern is the assurance that the fuse will not prematurely open thereby isolating c circuit unnecessarily.

The existing sample test described in Specification 4.8.4.1.a.2 is a resistance

=easurement of the fuse against the =anufacturer's design resistance.

Manufacturers , hcwever , from time-to-time change fusable materials or make other design changes which will change the design resistance tolerance. These changes are not announced to the users and are generally not distinguishable by unique part numbers or other physical changes since the fuse protective rating is ret changed. Resistance values =easured during the test could then lead one to an erroneous conclusion regarding the fuse's condition.

! Pega 3 SSES PLA-1430.

ER 100450 File 841-8

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Mr. A. Schwencer, Chief The proposed change described herein is to replace all pri=ary contain=ent

. protection fuses periodically with new fuses. The replacement fuses are resistance tested and certified by the manufacturer. This change will reduce maintenance ti=e to perform the work and reduce fuse pre =ature opening caused by component aging. Since all fuses used'in primary containment penetration protective circuits will be periodically replaced with fuses tested to the proper resistance instead of a sample testing of fuses to an uncertain resistance value, plant safety will be increased by this change.

ITEM 8:

Specification 4.6.1.7 Proposed Change: Revise per Attachment 8 Justification for Change: The purpose of the proposed change is to update the Specification to the design drawings. These changes have no impact on the safe operation of SSES; they merely reflect the actual configuration of the plant.

We have determined this proposed amendment to be Class IV in nature and have enclosed the appropriate fees pursuant to 10CFR170.

Very truly yours, (Lyed) N. W. CU3HS N.W.durtis Vice President-Engineering & Construction-Nuclear Attachments ,

cc: R. L. Perch - USN2C

, ATTA CH MDJ T - l _

ADMINISTRATIVE CONTROLS 2.-

REVIEW (Continued)

Proposed changes to Appendix A Technical Specifications or this d.

Operating License.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety,
i. Reports and meetings minutes of the PORC.

AUDITS 6.5.2.3 Audits of unit activities shall be performed under the cognizance of the SRC. These audits shall encompass:

3 u; a. The conformance of unit operation to provisions contained within the Appendix A Technical Specifications and applicable license conditions at least once per 12 months.

l b. The performance, training and qualifications of the entire unit staff at least once per 12 months. .

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, l

at least once per 24 months.

e. The Emergency Plan and implementing procedures at least once per '
4' months.

12.

f. The Security Plan and implementing procedures at least once per 24 months.

c Any other area'of unit operation considered appropriate by the SRC or the Senior Vice President-Nuclear.

h. The Fire Protection Program and implementing procedures at least
=r once per 24 months.

g y. NidOON& \ v. y i SMSr4EuANNA - UNIT 1 6-11

d CH NE AJT [ ADMINISTRATIVE CONTROLS j.h REVIEW (Continued) Proposed changes 'to Appendix A Technical Specifications or this 

                                  ~

d. Operating License.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g. Events requiring 24 hour written notification to the Commission.
h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
                     -i. Reports and meetings minutes of the PORC.

AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRC. These audits shall encompass: 

       ,i              a. The conformance of unit operation to provisions contained within the
                      ~

Appendix A Technical Specifications and applicable license conditions at least once per 12 me.nths.

b. The perfor. nance, training and qualifications of the entire unit staff,at least once per 12 months. ,
c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e. The Emergency Plan and implementing procedures at least once per 24 months.
f. The Security Plan and implementing procedures at least once per
                            .l:.> months.                                                          l
12. j
g. Any other area of unit operation considered appropriate by tha l SRC or the Senior Vice President-Nuclear.

l

h. The Fire Protection Program and implementing procedures at least g

once per 24 months.

( A-Trunussr.3 ADMINISTRATIVE CONTROLS lianay%f Inb4 Brad,OW.' n d Rhu. % y,,, w-MONTHLY OPERATING REPORTS l 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety ^ "/ " l relief valves, shall be submitted on a monthly bcsis to the AL

  • r I
7, u -u-m u3pe - M , U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made l l effective. In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC. REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully In case of corrected or supplemental i describe final resolution of occurrence. reports, a licensee event report shall be completed and reference shall be made to the original report date. PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.d The types of events listed below shall be reported within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Regional Administrator of the Regional Office, or his designate no later l ' than the first working day following the event, with a written followup report within 14 days. The written followup report shall include,,as a minimum, a Information provided on the completed copy of a licensee event report form. licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances i surrounding the event. .

a. Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint speci-fied as the limiting safety system setting in the technical specifica-tions or failure to complete the required protective function.
b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.

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c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary contairment.

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TTACMMGA3T SPECIAL TEST EXCEPTIONS n

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3/4.10.5 OXYGEN CONCENTRATION LIMITING CONDITION FOR OPERATION 3.10.5 The provisions of Specification 3.6.6.4 may be suspended during the performance of the Startup Test Program until either the required 100% of RATED THERMAL POWER trip tests have been completed or the reactor has operated for 120 Effective Full Power Days.* . APPLICABILITY: OPERATIONAL CONDITION 1. ACTION With the requirements of the above specification not satisfied, be in at least STARTUP within 6 hours. SURVEILLANCE REOUIREMENTS a 4.10.5" The Effective Full Power Days of operation shall be verified to be less than 120, by calculation, at least once per 7 days during the Startup Test Program. f rp

  • E % fr a. 1. ic eri2. go. g 6

[TMMG>J T h w. m REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.
b. 5 gpm UNIDENTIFIED LEAKAGE.
c. 25 gpm total leakage averaged over any 24-hour period.
d. 1 gpm leakage at a reactor coolant system pressure of 1000 t 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.
6. 2 gm teCrease. := UNabEelrefiEL LCaux,g ovw a 4 -home sar ve.il amec, er.ed .

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTOOWN within the next 24 hours.

O

t b. With any reactor coolant system leakag.e greater than the limits in b
  • and/or c, above, reduce the leakage rate to within the limits within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
c. With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
d. With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-1. inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm pressure at least once per 12 hours; restore the inoperable monitor (s) to OPERABLE status within 30 days or ba in at least HOT SHUTOOWN within the next 12 hours and in COLD SHUTCOUN within the following 24 hours.
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We'4 s7 rew,e coo lw sy ch (cal.5g ln efe,y,, 5ge m - M M lu"*r e abeve., W U) N s..,c o f leds)t raus e af not sevice. i.s ScM.'t:ve Tp e. 204 or s a u ,t d ,4,. sh' teu 5:4cci d m', 4 haas o- h e. h' ia d leac+' Hof 54a n eW d E+h.' +1v. nev+ 12.he.cs u /, COLD saurmJ J, g & .gn,,,( 2+ geo,,,

ATracsncar 5s ~ REACTOR'C00LANT SYSTEM .( SURVEILLANCE REQUIREMENTS C 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a. Monitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per Jf' hours, and I
      .                                                          4                           L
b. Monitoring the drywell floor drain sump ' level at least once per I
                      }{' hours.

4-4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit: ,

a. At least once per 18 months, and
b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into 4ffD OPERATIONAL CONDITION 3. Qej 4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with the alarm setpoints per Table 3.4.3.2-1 by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
b. CHANNEL CALIBRATION at least once per 18 months.

TIAC4 % JT b

  • Le C 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH .

LIMITING CONDITION FOR OPERATION 3.9.1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or 

      . Refuel position.       When the reactor mode switch is locked in the Refuel position:

I

a. A control rod shall not be withdrawn unless the Refuel position one-rod-out interlock is OPERABLE.
b. CORE ALTERATIONS shall not be perfor=ed using equipment associated with a Refuel position interlock unless at least the following associ-ated Refuel position interlocks are OPERABLE for such equipment.
                                                  \

All rods in. 1.

2. Refuel platform position.

l 3. Refuel platform hoists fuel-loaded.

4. Fuel grapple position.
5. Service platform hoist fuel-loaded.-

APPLICABILITY: OPERATIONAL CONDITION 5* #,g , dews ACTION: l t I a. With the reactor mode switch not locked in the Shutdown or Refuel position.as specified, suspend CORE ALTERATIONS and lock the reactor mode switch in the Shutdown or Refuel position.

b. With the one-rod-out interlock. inoperable, lock the' reactor mode switch l

in the Shutdown position.

c. With any of the above required Refuel position equipment interlocks inoperable, suspend CORE ALTERATIONS with equipment associated with the inoperable Refuel position equipment interlock. ,
  • See Special Test Exceptions 3.10.1 and 3.10.3
           # The reactor shall be maintained in CPERATIONAL CONDITION 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
            #JThe reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that all control 7

rods are verified to remain fully inserted by a second licensed operator 2% or other technically qualified member of the unit technical staff.

ffAIMGNT ] ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

2. .o- .,~

a cting and functionally testing a representative sam ' i of each u of fuse on a rotating basis. sample of fuse Each repree eative i 11 include at least 10% of al ses of thati type. The functionas st shall consist of - on-destructive resistance measurement tes hich demone tes that the fuse meets its manufacturer's desig. *i'. la. Fuses found inoperabl e during these functional testin 2 a Fe replaced with OPERABLE fuses prior to resuming ation. For fuse found inoperable during these functi tests, an additional resentative sample of at least 1 Y all fuses of that type shall b ^ nctionally tested un no more failures are found or all fuses o at tyon ve been functionally tested.

b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with proceduras j prepared in conjunction with its manufacturer's recommendations.

l cy td,5 tu v. .f & G s p ues 5 gr; By c e a c w ws.J.n ma b of e + p . Han f ~c%c -lat dda is G 'ct na u Q.(, ca + ,k of +ks. L5 b +ib cmc +y.

Arracunear 8 . CONTAIN$ENT SYSTEMS - DRYWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.7 Drywell average air temperature shall not exceed 135*F. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ACTION: With the drywell average air temperature greater than 135 F, reduce the average air temperature to within the limit within 8 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 nours. SURVEILLANCE REOUIREMENTS N 4.6.1.7 The drywell average air temperature s' hall be the c.rithmetical average of the higher temperature at a minimuin of 3 of the following elevations and shall be determined to be within the limit at least once per 24 hours: Elevation Azimuth . i

a. 797'8" 10;^, 20." I t o*, 2.9 6"
b. 752'2" CO^, 2:7 70* j270 725' or 711' "0^, ;;;' 265*, 270 c.
d. 711' or 720' 00", .^.-Y CO , 8

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                                                                                                   \Q encuemmu - nun 1                    sufLA o

o 4 BEFORE THE UNITED STATES NUCLEAR REGULATORY COBeilSSION In th'e Matter of  : PENNSYLVANIA POWER &  : Docket No. 50-387 

!               LIGHT COMPANY i

AMENDMENT No. 15 FACILITY OPERATING LICENSE NO. NPF-14 SUSQUEHANNA STEAM ELECTRIC STATION UNIT NO. 1 i Licensee, Pennsylvania Power & Light Cc=pany, hereby files Amendment No. 15 to its Facility Operating License No. NPF-14 dated July 17, 1982. This amendment contains revisions to Appendix A of License No. NPF-14, the Susquehanna SES Unit One Technical Specifications. PENNSYLVANIA POWER & LIGHT COMPANY BY: n ( ku d L w U (t ? i N. W. Curtis Vice President - Engineering and Construction - Nuclear Swor g' "o and subscribed before me this i cdll!'D'{2L[,1982. 

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Motary Pcblic 

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  • to a41 Lc.tu cogn:y, ga, LdAmmistica E.<;:p.es .f:n.41936

Rav. 1 D' . Py .,.2. 

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                                 ..           *.91.17 -f NRC COR'RESPONDEIICE REVIEW To: //..$</me,2-                                                    /2/9/S:-         PLA- /47C
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Date: Subjec : Ne ec u</ / ben'

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8 P '. in . : 'icdification Required? Yes x vNo . If Yes: Da e Filed Responsible .',Ianager: Signature: Cot =ents and Cc=.itments Rb&olution i 

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Rev. 1 (g/E )

UNITED STATES OF AMERICA 

                               . NUCLEAR REGULATORY COMMISSION
                                               ~                             "          ~

( B E F O R E T H Er' A' TONIC ShTETY AND IiICENSING hEPEAIi BOARD _. ' In the Matter of ) 

                                                                )

PENNSYLVANIA POWER & LIGHT COMPANY ) 

                                                                )

AND . ) Docket Nos. 50-387 

                                            ~

i ) 50-388

ALLEGHENY ELECTRIC COOPERATIVE, INC. )
                                                                )

(Susquehanna Steam Electric Station, ) Units 1 and 2) ) SERVICE LIST , Secretary of the Commission Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Board Panel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Thomas S. Moore, Esquire l Administrative Judge Docketing and Service Section 

  ' Atomic Safety and Licensing                            Office of the Secretary Appeal Board                                        U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission                    Washington, D.C. 20555 Washington, D.C.          20555 Stephen F. Eilperin, Esquire Dr. John H. Buck                                      Administrative Judge Administrative Judge                                   Atomic Safety and Licensing Atonde Safety and Licensing                              Appeal Board Appeal Board                                        U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission                   ' Washington, D.C. 20555 l Washington,'D.C. 20555 l

Susquehanna Environmental Advocates James P. Gleason, Esquire c/o Gerald Schultz, Esquire Administrative Judge Post Office Box 1560 513 Gilmoure Drive Wilkes-Barre, Pennsylvania 18703 l Silver Spring, Maryland 20901 ! Mr. Thomas J. Halligan, Correspondent Mr. Glenn O. Bright The Citizens Against Nuclear Dangers Administrative Judge Post Office Box 5 Atomic Safety and Licensing Scranton, Pennsylvania 18501 Board Panel U.S. Nuclear Regulatory Commission Ms. Colleen Marsh Washington, D.C. 20555 Box 558 A, R.D. #4 Mt. Top, Pennsylvania 18707 Dr. Paul W. Purdom Administrative Judge Atomic Safety and Licensing Appeal 245 Gulp Hills Road Board Panel Radnor, Pennsylvania 19087 U. S . Nuclear Regulatory Commission Washington, D.C. 20555

Robert W. Adler, Erquira Department of Environmental Ragourcas Commonwealth of Pennsylvania 505 Executive House 

     ' Post Office Box 2357 Harrisburg, Pennsylvania    17120 James M. Cutchin, IV, Esquire Office of the Executive Legal i

Director U.S. Nuclear Regulatory Commission Wnchington, D.C. 20555 - DeWitt C. Smith i Diractor -l Pennsylvania Emergency Management Agancy Transportation and Safety Building Harrisburg, Pennsylvania 17120 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Department of Environmental Rasources Commonwealth of Pennsylvania Post Office Box 2063 Harrisburg, Pennsylvania 17120 Dr. Judith H. Johnsrud Co-Director . Environmental Coalition on Nuclear Power J 4 33 Orlando Avenue State College, Pennsylvania 16801 - r. e e}}

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