ML20024A314
| ML20024A314 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/02/1983 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Kanga B GENERAL PUBLIC UTILITIES CORP. |
| References | |
| CON-NRC-TMI-83-034, CON-NRC-TMI-83-34 NUDOCS 8306160682 | |
| Download: ML20024A314 (4) | |
Text
_
[.' ' 3 DISTRIBUTI0ti:
DN 50-320 C g,
N fiRC PDR Local PDR DCS TMI Site r/f June 2,1(183 TMI HQ r/f
~^
i f s (,
NRC/THI 83-03SJSnyder si
., m LHBarrett
'f
'\\.
TPoindexter
.J' " Doc.ket No.,,50-333 _
RWeller i
J' AFas ano
)
N M ]",lir.dct'or, TMI-2M',, kanc,P
~ '
\\
JWiebe
\\
\\
iir LChandler
'\\
4 uPU trucfear Corporation ACRS P. 0.; Box 480 HRDenton I&E.
fliddletwn, PA 17057 t)-
Service List
'lkiD$t'.- Kanga
. hubject,! Rev$w of Underhead Characterization Safety Evaluation Reports (SER)
N N
09fe ences:' (f)
B. K. Kat'ga to L. H. Barrett, same subject, dated i'l\\
May 19,~1983 (4410-83-0040)'
. _,j, s
v x
/(2)
B. K. Xanga to L. H. Barrett,'t.'ene subject, dated
,, N\\'
!!a)'25,1983 (4410-83-0098)
N
1 i
Tite flRC scaff,h.s rsviewed the referenced letters which transmits GPU's Safety Evaluatlon feports hi icwsring the water level in the reactor coolant system and conductina UMerband chah.cterization studies. We understand that the
'teference (1)?ty 4tas $2ubmitted with the assumption that the polar crane would he available f'or vTM removal, while the reference (2) SER assumes the polar
,1 s craneisnotavaihblegnda9 alternate plan was developed to remove the CRDM via a hoist system unocr ths missile shields.
v In order fo'r :ay st ff toi omplete the review of the subject SER's we have d
attached a l$st of questfons and clarification items for your response. The majority of'these items,9ere' disc (issed with your staff in the May 25, 1983
~'~
- recting. We are aware that $vo' Additiona'. SER's (i.e., Core Topographic
~ Deasurements and Core iampli,b) will be submitted as part of the additional underhead characterizatiW.teasurements. ' fly staff will review each of these on l. s.
s
,an individual basia../,
4 us
\\
't 2
)
Q,,
/
f i
I i
J-'
t Lake 11. Barrett
%*s
' f '~~,
Deputy P d. ram Director
,- 7 Till Program Office
~-
7,
's 1,
-70 Attach 1da!.: As Stated 1
s 3:
fSbsokhe!$88jjg y.
PDR n'
l
~ * " ' '. Tf:!I : P0..
.{11Jgf
?"' *
. w a......L..H3.'a,.r(e b
y
..p /~2/
J """.6/ Z /83..
6 Nac ronu na no-soi sacu oso OFFICIAL RECORD COPY
ATTACHMENT 1 QUES.TIONS/ CLARIFICATIONS ON SER Question:
1.
Section 2.2, Reactor Coolant Pressure Boundary states that a pressure retaining boundary will no longer be required after the initiation of the underhead characterization.
For example your staff stated that no gasket will be used for the flanged connection between the CRDM vessel flange and manipulator tube flange.
It is our position that cleanup steps such as underhead characterization, should preserve as much system flexibility as practicable to permit optimum response to unexpected conditions.
Specifically, we believe it is prudent to take simple steps to allow future reactor coolant system pressurization.
This would preferably include the use of a manipulator tube that can be sealed or other less desirable means, e.g., replacement of the manipulator tube with a blind flange.
Describe your proposed contingency plans for prompt reciosure capability.
2.
Section 3.1, (p. 7) you state, "The present general area dose rate on top of the service structure is 50 to 150 mrem /hr.
The increase in the general area dose rate on the top of the service structure of less than 20 mrem /hr is relatively small".
Based on the above, the potential increases in general area radiation levels resulting from lowering the RCS water level and removing a CRDM are considered acceptable. Measurements will be taken for varying water level conditions to assess the actual conditions with respect to the removed CRDM.
a.) Please describe the measurements (other than TLD) that will be taken for varying water level conditions to assess the actual radiation conditions with respect to the removed CRDM.
b.) Provide a description of the service structure area radiation monitoring system which was discussed during our meeting on May 25, 1983.
Please state the number of channels (monitoring locations) to be used in order to obtain dose rates at various points around the head and service structure.
3.
We note that you are in the process of shielding the service structure.
Do you intend to undertake the vessel radiation characterization before this shielding is completed? Please describe the considerations of the vessel radiation characterization, and the shielding program.
4.
In Section 4.4 (p. 16) you state that "the activities are not expected to increase the airborne activity in the containment atmosphere beyond that assumed in the calculation of releases...during decontamination activities....".
We find it difficult to relate airborne activities associated with work in the reactor vessel with your previous decontamination 6
activities.
Describe your considerations for the potential airborne activity (including alpha emmitters) associated with opening the vessel. Describe the air sampling program associated with the vessel characterization study objectives. Describe additional sampling efforts (smears, etc.) required to effectively assess all potential radiation hazards.
5.
Section 4.3.2.2, paragraph 1, provide clarification that an electrically locked out pump is an isolation boundary only when it is the source of driving head.
6.
Section 4.3.2.2 (a), describe your system for verifying a pressure differential exists including periodicity and any alarms.
7.
A few of the closed tagged-out valves will need to be operated to support other evolutions. What allowances and special precautions are being taken in this regard.
8.
Section 2.2, Reactor Coolant Pressure Boundary.
The manipulator tube material is aluminum, whereas most of the RCS is stainless steel.
Provide the basis for the compatability of the aluminum material considering expected chemistry conditions.
9.
Section 4.3.2.3, Sampling and Boron Measurements.
Describe your location (s) for RCS sample collection and the basis for these samples being representative of core boron concentrations.
- 10. Describe the increased radiation precautions necessary if placing the CRDM on the service structure instead of storage in the canal (polar crane not available).
- 11. Do you plan to remove more than one CRDM for the detailed underhead characterization (as discussed in Planning Study TP0/TMI-028).
Describe your plan and sequence for additional CRDM removal.
- 12. Describe your plans for meeting Technical Specification Surveillance requirements for those systems affected by the underhead characterization program.
- 13. Describe what chemistry / radiochemistry consid9 rations (i.e.,
turbidity, crud burst, fission products spikes, pH effects) and controls for RCS processing were made recognizing the oxidation conditions within the RCS will change during the underhead characterization.
14.
Provide supporting data that demonstrates the recirculation rates discussed in Section 4.6 exist.
Y
J. Allen, Acting WILLIS SIISV. $1TE MANAGER SEGIONAL ADMINISTRATOR. SEGIDN !
U.S. DEPARTMENT OF ENERGY U.S. NUCLEAR REGULATORY COMM15510H P.O. ROX 88 331 PAtt AVE.
MIDDLETOWN. PA 17057=4311 LIN3 OF PSUSSIA. PA. 19404 DAVID J. MCEOFF JD 3 F. WOLF. ESO.. CHAIRMAN.
DIVISION OF TMIEE MILE ISLAND PROGRAMS ADMINISTRAilvt JUDGE NE=23 3A09 SNEPNEED ST.
U.S. DEPASTMENT OF ENERGY CHEVY CMast. MD.
20015 WASHINGTON. DC. 20545 Dt. OScat N. pat!S WILT 1AM LOCMSTET ADMINISTRATIVE JUDGE 104 DAVEY LABotATORY ATOMIC SAFETY AND LICENSING PEMMSYLVANIA STATE UNIVERSITY BOARD PANEL UNIVER$17Y PAtt, PA 16802 U.S. NUCLEAR 'EGULATORY COMMISS!DN kASHINGTON. D.C. 20555 RANDY MYERS. EDITORIAL Dt. FREDERICE J. SHON 812 MARKET ST.
ADMINISTRATIVE JUDGE Matt!$5UGG. PA 17105 ATOMIC SAFETY AND LICINSING U.S. NUCLEAR REGULATORY COMMIS$10N togEnf 3. BORS'UM BOAtD PANEL UASHINGTON. D.C.
20555 SABCOCK & WILCDI NUCLEAR POWER GENERATION DIVIS10M KAt!N W.
CARTER SUITE 229 ASSISTANT ATTORNEY GENERAL 7910.WOOOMONT AVE.
505 EXECUTIVE MOUSE BETWESDA. MD.
208t4 P.O. BOX 2357 Matt!$ BURG. PA 17120 JUDITH A.
DOESEY
- 04. JUDITH N.
JONNStVD SUITE 1632 ENVitOMMENTAL COALITION ON PHILADELPNIA. PA 19teT NUCLEAR POWER LINDA W. LITTLE 433 ORLANDO AVE.
5000 NERMITASE D8.
STATE COLLEGE PA 1640g SALE!GN. NC 27412 GEORGE F. T10W8t!DGE. ESS.
$NAW. PITTMAN, POTTS AND MARV!N !. LEWIS 6504 StADFORD TEtaACE ftOW8 RIDGE PHILADELPNEAe PA 19149 1800 M. ST.. NW.
WASHINGTON. DC 20036 ATOMIC SAFETY AND LICENSING SOARD PANEL 183 VALLEY RD.
ETTEas. PA 17319 U.S. NUCLEAR REGULATORY COMMISSION WASHINGTON. DC 20555 J.B. LIBERMAN. ESOUIRE ATOMIC SAFETY AND LICENSING APPEAL PANgg SERLACE. ISRAELS. LIBERMAN U.S. NUCLEAR REGULATORY COMMISSION 26 St0ADWAV WASHINGTON. DC 20555 MIN YORE. NY 10004 WALTER W. COMEN. CONSUMER ADVOCATE SECRETARY U.S. NUCLEAR REGULATORY COMMISS!DN DEPARTMENT OF JUSTICE ATTN CHIEF. DOCKETING & SERVICE BRANCH STRAWetatY SOUARE, 14TN FLOOR Matt 158UAG. PA 17127
. WASHINGTON. DC 20555 ECWARD 0. S?6tTZ BOARD OF SUPERV150tS r.t. LAIRY NOCHENDONER LONDONDEttY TOWMSMIP DAUPMIN COUNTY COMMIS$10NER RFD 91 GEYERS CMutCN RO.
P.O. BOX 1295 MIDDLETOWN. PA 17957 NAtt153URG. PA 17108-1295 903EST L. ENUPP. ESQUIRE l
JOHN E. MINNICN. CHAttPERSON.
ASSISTANT SOLICITOR l
DAUPNIH COUNTY SOARD OF COMMISSIONERS EMUPP AND ANDtENS l
DAUPMIN COUNTY COURTHOUSE P.O. 3tOI P l
F8CNT AND MARKET STREETS 40? M. ftONT ST.
Matt!SEUAG. PA 17101 NAtmStAURG. PA 17108 DAUPMIN CCUNTY OFFICE OF EMERGENCY JONN LEVIN. ESQUlst PREPatEDNESS PENNSYLVANIA PUBLIC UTILITIES COMM.
CCUtf NOUSE. ROOM 7 P.O. Box 3265 FRCMT & MARKET STREETS NAtt158URG. PA 17129 Natt!SBURG. PA 17101 NONQtASLE MARE COMEM U.S. ENVlt0NMENTAL PROTECTION AGENCY 512 E=E MAIN CAPITOL SUILDING REGION !!! QFFICE NAtt1SBURG. PA 17129 ATTNs EIS COORDINATOR CURT!S BUILDING ($!xTN PLoct3 j
& WALNUT STREETS 6TN PN!LADELPHIA. PA 19106 TNCMAS M. CERUSEY DIRECTOR BUREAU OF RADIAT10N PROTECTION CEPARTMENT OF ENV!t0NMENTAL RESOURCES P.O.
801 2C63 Natt155UtG. PA 17120 Dav!D NESS OFFICE OF ENW120NMENTAL PLANNING DEPAt1 MENT OF ENyttDNMENTAL RESCURCES
~
_