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{{#Wiki_filter:1 DOCKETED UNC SHAW,Pli MAN, POTTS & TROWBRIDGE A PARTN8mSMIP OF pmOFESSIONAf.COppORATIONS
{{#Wiki_filter:}}
                                                  ..oo . .r.wr, N. ..                '83 FEB 15 NO:30 TELtx                            WASHINGrON, D. C. 20036                                TELECOPlan emes (sM AwLAw wSM)                                                                    2043 0244099 & estales CA BLE "SM AwbAw''
                                                                                          ~ $':          1 *7";* ',.._
                  -                                                                        ,1 ! . . a < AASBBFAR 100
                                                                                  ' i, TELEPHONE                                                                          ![!$ ?90e saa eO78
            =Om .aa420 noscar c. zAMLEn. P. c.                February 8, 1983 Gary J. Edles, Esquire Chairman Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555                                      .
Dr. John H. Buck Attmic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Reginald L. Gotchy Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1)
Docket No. 50-289 (Restart)
 
==Dear Chairman Edles and Administrative Judges Buck and Gotchy:==
 
Pursuant to the procedures outlined in Licensee counsel's letter to the Appeal Board of October 1, 1981, enclosed is a copy of a February 2, 1983 letter from H.D.
Hukill, Vice President TMI-1, to J.F. Stolz, Office of Nuclear Reactor Regulation.
Mr. Hukill's letter sets forth a proposed alterna-tive method for ensuring that potential exposures from fuel handling accidents at TMI-1 conform to current regulatory guidelines. As reflected in the Licensing Board's Partiel Initial Decision on Plant Design and Procedures, Unit Separation, and Emergency Planning Issues, dated December 14, 1981, Licensee comIritted to upgrade the Fuel Handling 8302160293 830208 PER ADOCK 05000289                                                                                            m
  &                      PDR DSOc
 
SHAw, PITTMAN PoTTs & TRO'NBRIDGE a paamcas.u or ,=orcosionat co ,oneous l
Gary J. Edles, Esquire Dr. John H. Buck Dr. Reginald L. Gotchy February 8, 1983 Page Two Building Ventilation System to include a new engineered safety feature ("ESF") filter system prior to the first refueling outage after restart. The purpose of this upgrade was to bring TMI-l into compliance with the guidance set forth in Regulatory Guide 1.52 (Rev. 2, Ma rch 1978) . Upon further analysis, Licensee now proposes tc satisfy Regula-tory Guide 1.52 guidance b3 2dministratively revising fuel handling procedures to preclude the movemeat of irradiated fuel into the Fuel Handling Building until 12 days after shutdown.            Calculations performed in accordance with NRC Staff guidelines show that such a delay prior to fuel move-ment in the Fuel Handling Building will allow sufficient decay time to keep the dose from postulate 6. accident within i          the numerical guidelines of Standard Review Plan ("SRP")
j          section 15.7.4.
Mr. Hukill's letter requests modification of Licensee's commitment to install an ESF filter system.
Respectfully submitted, Robert E. Z ler Counsel for Licensee cc:      Service List l
l I
l
                ,      w  -- --                v -
 
ATTACIL*fENT 1 i
Assumption and Key Parameters
: 1. Power level of 2535 MWt
: 2. 288 hour decay period
: 3. Peaking factor of 1.68
: 4. 10% of noble gases and iodines from a damaged fuel cssembly (208 fuel pins)
: 5. All the filcrations systems in the fuel handling building are inoperable.
: 6. Iodine partition factor of 100.
: 7. Breathing rate of 3.47 x 10-4 3m /sec.
: 8. At=ospheric diffusion factors were based on Pasquill stability condition F, wind speed of 1.75 mph:
X Q        at site boundary = 6.8 x 10~ eec/m 3 X
_        Q,      at LPZ                                = 1.3 x 10-4sec/m 3
 
  -      ~
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pmunqu, ag                                                                                GPU Nuclear Corporation yf y'        t Mg spam          as                                                      Post Office Box 480 L. J. )l-8 W Mw -                B                                                        Rome 441 South Miotetcwn, Pennsylvania : 7057 717 944-7621 TELEX 84-2386 Writes"s Direct Dial Numcer:
February 2, 1983 5211-83-023 Office of Nuclear Reactor Regulation Attn:    J. F. Stolz, Chief Operating Reactor Eranch No. 4 Division of 1.icensing U. S. Nuclear Regulatory Commission Washington, D.C.      20555 gear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)                                          ,
Operating License No. DPR-50 Docket No. 50-289 Engineered-Safety-Feature (ESF) Filter System Tne ASLB Partial Initial Decision (PID) on Plant Design and Procedures dated D2cember 14, 1981 states at Paragraphs 1265 and 1326(a) that GPUN chall upgrade the Fuel Handling Euilding Ventilation System to include a new engineered safety facture (ESF) filter system prior to the first refueling outage. The FID also set:cs that this system will n.aet the guidelines of Regulatory Guide 1.52 (Rev.
              ', harch 1978) and must be in operation whenever Unit 1 fuel movements are in i
l progress. We request that TMI-1 be relieved of the obligation of meeting this j              requirement.
L I              Ancivses for the radiological consequences of a postulated TMI-l fuel handling                                  '
I              accident (FHA) have been performed using the assumptions outlined in Attach =ent
: 1. These assumptions have inccrporated the guidance of SRP. 15.7.2 and of Regulatory Guide 1.52, Rev. 2 (March 1978) with the exception of the item noted oelcw. The results of these analyses are given below:
SRP Exclusion                      15.7.4 Boundary            LPZ        Limit          10 CFR 100 Limit Thyroid                  75          14.3            75                      300 (rem)
              ' thole Body Dose
              .                      0.15          0.03            6.25                      25 l                (rem) l As can be seen from the assumptions in Attschnent 1, an elapsed time period of twelvt (12) days (288 hours) has been used to provide additional decay time for I              tafimetdyc gasec, and thus, reduced integrated doses (thyroid /whole body) ct
!              L.-th the exclusion boundary cnd low population zone. The time period mentioned GPU Nuciear Corporation is a subsidiary of tne GeretalFuthe Ut'i ties Corce atibn C3^ %C..-,-            -
O NW U %./ l MQ l                              4e
 
Mr. J. F. Stolz                                                5211-83-023 above represents the time elapsed between reactor shutdown (beginning of hot shutdown) and when the first spent fuel assembly is to be transferred into the Fuel Handling Building. Current defueling procedures will be amended to preclude moving irradiated fuel into the Fuel Handling Building before 12 days after shutdown.
The above analysis confirms the adequacy of the TMI-1 design with respect to 4
off-site impacts. The ventilation separation modifications inp3 ace at restart assures no adverse impacts inplant from a fuel handling accident in the FHB.
The co=:nitment allows an alternative to the conditions imposed by the ASLB in Paragraph 1265.
Sincerely,
                                                                          . D. u ill Director, TMI-l HDH:LWH:vj f Attachment cc: J. Van Vliet R. C. Hayner m &
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                                            ,gw.  ,                    -              e  -
 
l                  - -
UNITED STATES OF AMERICA l    ,                          NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD l
i          In the Matter of                                  )
                                                              )                                              ^
l          METROPOLITAN EDISON COMPANY                      )      Docket No. 50-289
                                                              )            (Restart)
(Three Mile Island Nuclear                        )
Station, Unit No. 1)                              )
SERVICE LIST Gary J. Edles, Esquire                          James M. O? rhin, IV, Esquire Chai man                                        Office of the W+4ve Iagal Diractor Atcmic Safety and Licensing Appeal              U.S. Nuclear Regulatory Commission Board                                          Washington, D.C. 20555 U.S. Nuclear Regulatory Ccumssicn Waahington, D.C. 20555                        Docketi.g and Service Section Offi    of the Secretary Dr. John H. Buck                                U.S. Niv-laar Regulatory Ccmnission Atcmic Safety and Licensing Appeal              Washingtcn, D.C. 20555 soard U.S. Niv laar Reculatory Camissicm              John A. Invin, Esquire Washingtcn, D.C. 20555                          Assistant Cbunsel Pennsylvania Public Utility Ca mission Dr. Beginald L. Gotchy                          P.O. Box 3265 R?.cmic Safety and Licerasing Appeal            herinhurg, Pennsylvania 17120 Board U.S. Nuclear Regulatory Onmission                Ibud Adler, Esquire Washington, D.C. 20555                        Assistant AL W wey C - rmi 505 h tive House Ivan W. Smith, Esquire                          P.O. Box 2357 Olairman                                        h rriahurg, Pennsylvania 17120 Atcnic Safety and Li nsing Board U.S. Nuclear Regulatory Commissim                Ms. Iouise BraMnrd Waahington, D.C. 20555                          'IMI AIERP 1011 Creen Street Dr. Walter H. Jc:: dan                          Farriahurg, Pennsylvania 17102 Atcmic Safety and Licensing Board l
Panel                                          Ellyn R. WGs, Esquire l          881 West Outer Drive                            Harnon & Weiss Ridge,                    37830                            , N.W. Suite 506 C    Atcmic Safety and Licensing Board                Steven C. Sholly l                                                            Union of Cone *med Scientists Panel 1346 Connecticut Avenue, N.W. , Suite 1101 5000 Hennitage Drive l          Raleigh, North ravnlira 27612                    Washington, D.C. 20036 i
l l
l
 
Jordan D. Cunningham, Esquire 2320 North Second Street Harrieurg, Pennsylvania 17110 ANGEE/'IMI PIBC 1037 Maclay S* m t Harriahrg, Pennsylvania 17103 William S. Jordan, III, Esquire Harmon & Weiss 1725 Eye Street, N.W., Suite 506 Washington, D.C.          20006 G auncey Kepford Judith H. Johnsrud I
Env11.w.6ad.al Coalition on Nuclear Power 433 Orlando Avenm State Cbilege, Pennsylvania 16801 l            Marjorie M. Aanodt
      ,      R. D. 5 Q:stesville, Pe m lvania 19320 w
l                                              -
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Revision as of 08:41, 31 March 2020

Forwards Hd Hukill 830202 Ltr to Jf Stolz Re Proposed Alternative Method for Ensuring That Potential Exposures from Fuel Handling Accidents Conform to Current Regulatory Guidelines.Fuel Handling Procedures Revised.W/Svc List
ML20064N638
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/08/1983
From: Zahler R
METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Buck J, Edles G, Gotchy R
NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
References
NUDOCS 8302160293
Download: ML20064N638 (5)
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