ML20217H074
| ML20217H074 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/30/1997 |
| From: | Callan L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Goodling B HOUSE OF REP. |
| Shared Package | |
| ML20217H078 | List: |
| References | |
| NUDOCS 9708080211 | |
| Download: ML20217H074 (13) | |
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NUCLEAR REGULATORY COMMISSION g
o WASHINGTON, D.C. 30866 4001 July 30, 1997 The Honorable Bill Goodling Member. United States House of Representatives 2020 Yale Avenue Camp Hill, PA 17011
Dear Congressman Goodling:
I am responding to your letter of June 25, 1997, to Dennis Rathbun, of the U.S. Nuclear Regulatory Commission (NRC) in which you forwarded a concern of l
your constituent. Ms. Jane Lee, that the local NRC officials are not pro >erly monitoring the recent incident which occurred on June 21, 1997, at the T1ree Mile Island Plant. Unit 1 (TMI-1).
Ms. Lee stated that she believes the event is much more severe than originally reported by the media.
On June 21,1997, at 12:14 p.m.. the TMI-1 reactor automatically tripped from full power due to the failure of one of the output breakers on the main turbine electrical generator. All offsite power to the facility was also unexpectedly lost.
This event had no impact on public health and safety as plant safety systems performed as designed. All the control rods fully inserted to stop the nuclear reaction.
The emergency diesel generators automatically started and provided power to site loads and the emergency feedwater pumps automatically started to remove decay heat.
However, due to the loss of off-site power for over 15 minutes, the licensee declared an unusual event and properly reported it to the NRC Operations Center at 12:52 p.m.
NRC personnel at Headquarters and in Region I monitored the licensee's response to this event from their respective incident response centers, and the NRC resident inspector reported to the site to observe plant and licensee activities. Offsite power was restored to the plant at 1:44 p.m.
Shortly thereafter, all four reactor coolant pumps returned to operation and the licensee declared the unusual event terminated.
On June 23, 1997, an additional ins)ector was sent to the site to assess, among other things, the design capa)ility and testing of the new replacement generator output breakers.
The plant remained in a hot shutdown condition until the required testing and related corrective actions were completed. The 4'N 5)'
ins)ectors' findings and observations concerning this event will be contained in 4RC Inspection Report No. 50-289/97-06, which will be forwarded to you when it is issued in mid-August 1997.
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The Honorable Bill Goodling The media report referred to by Ms. Lee focused primarily on two issues:
- 1) whether.a radioactive release occurred and 2) 3 of the 69 control rods j
-insertion times exceeded the maximum allowable 1.66 seconds specified in the facility Technical Specifications (TS).
With respect to the first issue. the licensee dispatched field radiation monitoring personnel during this event, Field sampling results did not indicate any radiation levels above normal background radiation levels. This result was consistent with the low levels of primary coolant activity and the primary-to secondary leakage rate. Prior to and during this-event, the leak rate, which is logged every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and monitored continuously by radiation
. monitors, was non-detectable. The second issue involved control rods that had insertion times slower than the TS value of 1.66 seconds, There were actually four, vice three, control rods which displayed slower than allowed insertion times. The slowest insertion time observed was 2.-172 seconds.
The licensee's analysis assumes, conservatively, that the average insertion time for the 69 control rods is 3.0 seconds, which ensures that adequate shutdown margin is maintained. All the control rods were subsequently tested before restart of the plant and were confirmed to be in compliance with the TS requirements.
Also, these rods are slated to be modified during an upcoming refueling outage to address a design-issue that, over time, can lead to slower rod insertions.
In summary, the )lant responded as designed during this event, the radioactive release during t11s event was not significant, and both the licensee and the NRC staff promptly monitored this event and assessed the plant's configuration before the plant was restarted.
I trust that this letter is responsive to the concerns raised by Ms. Lee, Sincerely.
L.
eph allan Executive Director for Operations
The Honorable Bill Goodling '
The media report referred to by Ms. Lee focused primarily on two issues:
- 1) whether a radioactive release occurred and 2) 3 of the 69 control rods insertion times exceeded the maximum allowable 1.66 seconds specified in the facility Technical Specifications (TS).
With respect to the first issue, the licensee dispatched field radiation monitoring personnel during this event.
Field sampling results did not indicate any radiation levels above normal background radiation levels. This result was consistent with the low levels of primary coolant activity and the primary-to-secondary leakage rate.
Prior to and during this event, the leak rate, which is logged every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and monitored continuously by radiation rnonitors, was non-detectable. The second issue involved control rods that had insertion times slower than the TS value of 1,66 seconds. There were actually l
four, vice three, control rods which displayed slower than allowed insertion times.
The slowest insertion time observed was 2.172 seconds.
The licensee's analysis assumes, conservatively, that the average insertion time for the 69 control rods is 3.0 seconds, which ensures that adequate shutdown margin is maintained. All the control rods were subsequently tested before restart of the plant and were confirmed to be in compliance with the TS requirements.
Also, these rods are slated to be modified during an upcoming refueling outage to address a design _ issue that, over time, can lead to slower rod insertions.
In summary, the )lant responded as designed during this event, the radioactive release during t11s event was not significant, and both the licensee and the NRC staff promptly monitored this event and assessed the plant's configuration before the plant was restarted.
I trust that this letter is responsive to the concerns raised by Ms. Lee, Sincerely @cignedby L. Joseph b/MfrRwanan Executive Director for Operations DOCUMENT NAME: A:\\BUCKLEY\\G970504
- SEE PREVIOUS CONCURRENCE To receive a copy of this document indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" =No copy 0FFICE PDI-3/PM PDI-3/LA-(A)D:PDI-3 lECHED DD:DRPE D:DRPE-NAME BBucklrv*
EDunnington*
REaton*
BCalure*
JZwolinsk1*
BBoger*
DATE 07/23/97 07/23/97 07/23/97 07/11/97 07/14/97 07/15/9 7
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NAME-RZ1mmerman*
SCollins*
JCaMsii fr DATE 07/18/97 07/18/97 07/ E /97 07/3E; /97 0FFICIAL TECORD COPY
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S The Honorable Bill Goodling.,
The media report referred to by Ms. Lee focused primarily on two issues:
- 1) whether a radioactive release occurred and 2)' 3 of the 69 c'ontrol rods insertion times exceeded the maximum allowable 1.66 seconds pecified in the facility Technical Specifications (TS),
With respect to the first issue, the licensee dispatch field radiation monitoring personnel during this event.
Field sampli g results did not indicate any radiation levels above normal backgrou radiation levels. This result was consistent with the low levels of prima y coolant activity and the primary-to secondary leakage rate.
PriortoandAuringthisevent.-theleak l
rate, which is logged every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and monit ed continuously by radiation monitors, was non-detectable. The second iss involved control rods that had insertion times slower than the TS value of.66 seconds.
There were actually four. vice three, control rods which displ 'ed slower than allowed insertion times.
The slowest insertion time observ d was 2.172 seconds.
The licensee's analysis assumes, conservatively, that e average insertion time for the 69 control rods is 3.0 seconds, which ens es that adequate shutdown margin is maintained. All the control rods wer subsequently tested before restart of the plant and were confirmed to be compliance with the TS requirements.
Also, these roads are slated to be i dified during an upcoming refueling outage to address a design issue at over time, can lead to slower rod insertions.
In summary, the )lant respond d as designed during this event, the radioactive release during tais event, a d both the licensee and the NRC staff promptly monitored this event and a essed the plant's configuration before the plant was restarted.
I trust that this lette is responsive to the concerns raised by Ms. Lee, Sincerely.
L. Joseph Callan Executive Director for Operations DOCUMENT NAME: A:\\BUCKLEY\\G970504
- SEE PREVIOUS CONCURRENCE To receive a copy of this document indicate in the box:
"C' - Copy without attachment / enclosure "E' - Cooy with attachment / enclosure "N" =No copy 0FFICE PDI-3/PM PDI-3/LA (A)D:PDI-3 TECHED 00:DRPE D:DRPE NAME BBuckley*
EDunnington*
REaton*
BCalure*
JZwolinski*
BBoger*
DATE 07/23/97 07/23/97 07/23/97 07/11/97 07/14/97 07/15/9 7
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0FFICE ADPR:NRR D:NRR*
SCollins*
JCallan DATE 07/18/97 07/18/97 07/
/97 07/
/97 0FFICIAL RECORD COPY
/
The Honorable Bill Goodling The media report referred to by Ms. Lee focused primarily on tw issues:
- 1) whether a radioactive release occurred and 2) 3 of the 69 cpntrol rods insertion times exceeded the maximum allowable 1.66 seconds pecified in the facility Technical Specifications (TS).
With respect to the first issue, the licensee dispatched ield radiation monitoring personnel during this event.
Field samplin results did not indicate any radiation levels above normal background adiation levels.
This result was consistent with the low levels of primary colant activity and the primary-to-secondary leakage rate.
Prior to and du ing this event, the leak rate, which is logged every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and monitore continuously by radiation monitors, was non-detectable. The second issue volved four rather than three control rods that had insertion times sl er than the TS value of 1.66 seconds.
The slowest insertion time observed as 2.172 seconds. All the control rods were subsequently tested before estart of the plant and were confirmed to be in compliance with the TS r quirements.
The licensee's analysis assumes, conservatively, that th insertion time for each of the 69 control rods is 3.0 seconds, which ensur.
that adequate shutdown margin is maintained.
In summary. the )lant responded as de igned during this event, the radioactive release during t1is event was not si nificant, and both the licensee and the NRC staff promptly monitored this ent and assessed the plant's configuration before the plant was restarted.
I trust that this letter is res onsive to the concerns raised by Ms. Lee.
Sincerely.
L. Joseph Callan Executive Director for Operations DOCUMENT NAME: A:\\
EY\\G970504
- SEE PREVIOUS CONCURRENCE To receive a copy of thi document indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with attach nt/ enclosure "N' -No copy 0FFICE PDI-3/PM /
PDI-3/LA (A)D:PDI-3 TECHED DD:DRPE D:DRPE NAME BBuckleyr EDunnington*
REaton*
BCalure*
JZwolinski*
BBoger*
DATE 07/23/9/
07/23/97 07/23/97 07/11/97 07/14/97 07/15/9 0FFICE ADPR/NRR D:NRR*
SCollins*
JCallan DATE 07/18/97 07/18/97 07/
/97 07/
/97 L
OFFICIAL RECORD COPY l
The Honorable Bill Goodling /
Document Room located in the Law / Government Publications Section, State Library of Pennsylvania, Walnut Street and Commonwealth Avenue, Box 1601 Harrisburg, Pennsylvania 17105.
l With respect to the first issue, the licensee dispatched field radiation monitoring personnel during this event.
indicate any radiation levels above normal background radiatiFieldsamplingresults[didnot levels. This primary-to-secondary leakage rate observed at the plant bgfo,/pr result was consistent with the low levels of reactor coolant activity and the i
l re the event.
The second issue involved four rather than three control rodr that had insertion times slower than the TS value of 1.66 seconds. Thes)6westinsertiontime observed was 2.172 seconds. All the control rods werd subsequently tested 1
before restart of the plant and were confirmed to tg in compliance with the TS requirements.
The licensee's analysis assumes, f 3.0 seconds, which ensures cohservatively, that the insertion time for each of the 69 control rods that adequate shutdown margin is maintained.
In summary, the plant responded as designed during this event, the radioactive release during this event was not signif fant, and both the licensee and the NRC staff promptly monitored this even and assessed the plant's configuration I
before the plant was restarted.
I trust that this letter is respons ve to the concerns raised by Ms. Lee.
Sincerely, L. Joseph Callan Executive Director for Operations DOCUMENTNAlj: G:\\BUCKLEY\\G970.5
- SEE PREVIOUS CONCURRENCE To receive a copy of this document, Indicate in the bout "C" = Copy without attachment / enclosure "E".
Copy with attadhment/ enclosure "W" =No copy
/
0FFICE PDI-3/PM PDI-3/LA u ( A)D':PDJ43 TECHED*
DD:DRPE*
D:DRPE*
NAME
/ BBuckleyl%6 EDunningtoh" REatpV BCalure JZwolinski BBoger DATE /
07h3 /97 07/J3/97 07/ % /97 07/11/97 07/14/97 07/15/97 0FFICE ADPR:NRR*
D:NRR*
E00 OCA NAME RZimmerman SCollins JCallan DATE 07/18/97 07/18/97 07/
/97 07/
/97 0FFICIAL RECORD COPY
The Honorable Bill Goodling With respect to the first issue, the licensee dispatched fipid radiation monitoring personnel during this event.
Field sampling rpsults did not indicate any radiation levels above normal background radiation levels.
This result was consistent with the low levels of reactor cp61 ant activity and the primary-to-secondary leakage rate observed at the pipftt before the event, The second issue involved four rather than three contrpT rods that had insertion times slower than the TS value of 1.66 seconds. A e slowest insertion time observed was 2.172 seconds. All the control rods were subsequently tested before restart of the plant and were confirmefto be in compliance with the TS requirements. The licensee's analysis assunWs, conservatively, that the insertion time for each of the 69 control p6ds is 3.0 seconds, which ensures that adequate shutdown margin is maintain,ed, in summary, the )lant responded as des)gned during this event, the radioactive release during t11s event was not sigrtificant, and both the licensee and the NRC staff promptly monitored this event and assessed the plant's configuration before the plant was restarted.
l I trust that this letter is res onsive to the concerns raised by Ms Lee, Sincerely, L, Joseph Callan Executive Director for Operations DOCUMENT N
- - G:\\BUCKLEY\\G970502
- SEE PREVIOUS CONCURRENCE To receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure "E" =
copy with attachment / enclosure
- N" =No copy l, /
OFFICE PDI-3/PM PDI-3/LA (A)D: PD#W TECHED*
DD:DRPE*
D:DRPE*
NAME SBuckleylNG EDunnifigTDn REat#nfPr BCalure JZwolinski BBoger DATE
/ 07/K/97 07/pf/9h 07/ p/' /97 07/11/97 07/14/97 07/15/97 0FFICE ADPR:NRR N l):NR)N EDO OCA NAME/
RZimmerm # 5CM41ns JCallan DATE 07/18/97 44)7/ \\$/97 07/
/97 07/
/97 l
OFFICIAL RECORD COPY u
The Honorable Bill Goodling With respect to the first issue, the licensee dispatched field radj n
monitoring personnel during this event. Field sampling results 4td not indicate any radiation levels above normal background radiationjievels.
This result was consistent with the low levels of reactor coolant (tivity and the primary-to-secondary leakage rate observed at the plant befo -
the event. -The second issue involved four rather than three control rods at had insertion times slower than the TS value of 1.66 seconds.
The slowe t insertion time observed was 2.172 seconds. All the control rods were subsequently tested before restart of the plant and were confirmed to be ir/ compliance with the TS requirements. The licensee's analysis assumes, conserGatively, that the insertion time for each of the 69 control rods is 3.0 seconds, which ensures that adequate shutdown margin is mainta ned.
,g in summary, the >lant responded as igned duri g this event, the radioactive release during tiis event wastinsfartificanta a both the licensee and the NRC staff promptly monitored this event anfasses ed the plant's configuration before the plant was restarted.
Itrustthatthisletterisresponsivetoj he concerns raised by Ms. Lee.
Sincerely, L. Joseph Callan Executive Director for Operations
/
DOCUMENT NAME: G:\\_CKLEY\\G970504
- SEE PREVIOUS CONCURRENCE To receive a espy of this document. Indicate in the boas "C" = copy without attachment / enclosure "E" =
copy with attachment /enetosure "r suo copy 0FFICE PDI-3/PM'
,PCJ-3/LA4
( A)D; PDl'-3 TECHED*
DD:DRP1/ 0:DRPE #
NAME BBuckley(QR n'innninVton REatM W BCalure JZwol M k1 BBoger 6
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DATE 07//f/97 07/l4/97 07/ M /97 07/11/97 07/ I' /97 07/6/97 4
0FFICE ADES:BBM n D:NRR ED0 OCA NAME RWWWmW Stollins JCallan DATE 67//V/97 07/ /97 07/
/97 07/
/97
/
OFFICIAL RECORD COPY
/
A 3
Congressman B. Gooding '
With respect to the first issue above the license dispatc ed field radiation monitoring personnel during this event.
Field sampling r sults did not indicate any radiation levels above normal background.
his result was consistent with the low levels of reactor coolant act'i. ity and the )rimary-to-secondary leakage rate observed at the plant prior to the event.
T1e second issue, involved four rather than three control rodVwhose insertion rates were slower than the TS value of 1.66 seconds. The 6 west insertion rated observed was 2.172 seconds.
All the control r was subsequently tested prior to the restart of the plant and confirmed to,b in compliance with the TS requirements. The licensee's analysis assumes. conservatively, that of the insertion rate of each of the 69 control p6ds is 3.0 seconds which assures that adequate shutdown margin is maint rfed.
l In summary, the )lant responded as igned during this event, the radioactive release during tais event was insign'ificant and both the licensee and NRC staff promptly monitored this evohJtion and in the assessment of plant configuration prior to restart of the plant.
j I trust that this letter is sponsive to the concerns raised by Ms. Lee.
Sincerely.
L. Joseph Callan
/
Executive Director for Operations
/
/
/
/
/
t DOCUMENT NAME: G:\\BUCKLEY\\G970502 To receive a copy of this document, indicate in the box:
"C" = Ccpy without attachment / enclosure "E" - Copy with attachment / enclosure "N" -No copy OFFICE PDI-3/PM PDI-3/LA (A)D: POI-3 TECHED DD:DRPE D:DRPE NAME BBuckley EDunnington REaton 4. ($/ww JZwolinski BBoger 4
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DISTRIBUTION:
DOCKET FILE (50-289 w/ orig,inc)
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JCallan HThompson EJordan PNorry JBlaha SCollins/FMiraglia SBurns, OGC RZimmerman TMartin MSlosson, DRPM BBoger WTravers JZwolinski MThadani MBoyle (MLB4)
OGC OPA-OCA KBohrer SECY (CRC-97-0693)
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EDO Principal Correspondence Control al ad FROM:.
DUE: 07/16/97 EDO CONTROL: G9705 f
DOC DT: 06/25 97 R prosentative Bill Goodling TO:
Rathbun, OCA
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FOR SIGNATURE OF :
- GRN CRC NO: 97-0693 Callan-DESC:
ROUTING:
CONCERNS ABOUT THE MONITORING OF TMI NUCLEAR POWER Callan PLANT (Jane Lee)
Jordan Thompson Norry Blaha Burns DATE: 07/03/97 Miller, RI ASSIGNED TO:
CONTACT:
NRR Collins SPECIAL INSTRUCTIONS OR REMARKS:
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July 3,1997 NRR ACTION ypf NRR ROUTING:-
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.6-OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER:
CRC-97-0693 LOGGING DATE: Jul 2 97.
' ACTION-OFFICE:
EDO AUTHOR:
REP. BILL GOODLING AFFILIATION:
U.S. HOUSE OF REPRESENTATIVES ADDRESSEE:
RATHBUN, OCA LETTER DATE:
Jun 25 97 FILE CODE: ID&R S TMI
SUBJECT:
CONCERNS ABOUT THE MONITORING OF-TMI NUCLEAR POWER PLANT ACTION:
Signature of EDO DISTRIBUTION:
CHAIRMAN SPECIAL HANDLING: OCA TO ACK CONSTITUENT:
JANE LEE NOTES:
DATE-DUE:
Jul 18 97 SIGNATURE:
DATE SIGNED:
. AFFILIATION:
i d