ML030920014
| ML030920014 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/25/2003 |
| From: | Ronald Bellamy Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.03.035 | |
| Download: ML030920014 (6) | |
Text
En tergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Mike Bellamy Site Vice President March 25, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket 50-293 License No. DPR-35 Response to NRC Request for Additional Information, Deletion of Requirement from LCO 314.10.D, Multiple Control Rod Removal
REFERENCE:
- 1.
Entergy Letter, 2.02.064, Request for Amendment to the Technical Specifications, Deletion of Requirement from LCO 3/4.10.D, "Multiple Control Rod Removal" dated,-August 16, 2002 LETTER NUMBER:
2.03.035
Dear Sir or Madam:
Discussions with the NRC indicated that additional information was needed to complete their review of Entergy's Request for Amendment to Technical Specifications 3/4.1 0.D, "Multiple Control Rod Removal" (Reference 1). Attachments to this letter provide the requested additional information.
The inclusion of the NRC staff requested change provides additional conservatism during multiple control rod removal and reload operations. This response does not invalidate the no significant hazard conclusions previously submitted in the original submittal (Referencel).
If you have any questions or require additional information, please contact Mr. Bryan Ford, Licensing Manager, at (508) 830-8403.
,Aco I 203035
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Letter Number: 2.03.035 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 25th of March 2003.
Sincerely, Robert M. Bellamy Attachments: 1.
2.
Response to Request for Additional Information -1 page Proposed Technical Specification (mark-up) - 1 page cc:
Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Robert Walker Radiation Control Program Commonwealth of Massachusetts Exec Offices of Health & Human Services 174 Portland Street Boston, MA 02114 Mr. Steve McGrail, Director Mass. Emergency Management Agency 400 Worcester Road P.O. Box 1496 Framingham, MA 01702 203035
ATTACHMENT 1 LETTER NUMBER 2.03.035 Response to Request for Additional Information Proposed Changes to TS 3/4.10.D, "Multiple Control Rod Removal" Requirements 203035
Response to Request for Additional Information NRC Request:
Please include a condition in TS 3.1O.D.1.d stating that no fuel is loaded into the reactor core during multiple control rod removal operations.
Response
Pilgrim has proposed Specification 3.1 O.D.1.d, stating, " No fuel is loaded into the reactor core."
to minimize the possibility of fuel loading errors during multiple control rod removal operations. provides this proposed specification change.
The proposed specification prevents fuel load during multiple control rod removal operations to prevent inadvertent criticality. This additional restriction adds conservatism and is consistent with the current Technical Specification Bases.
203035
ATTACHMENT 2 LETTER NUMBER 2.03.035 Proposed Technical Specification (Mark up)
TS Page 3/4.10-3 203035
I LIfrTTNG CONDITIONS FOR OPFBATION SlPTVE-LUt
,F 'ErEOUIRMENTS 3.10 CORE ALTERATIONS (Gon;)
Mul-iole Cantro1.od RemOvat (Cant)
- b. Thve source rznve mqni.orS (SRM) are onerable Snecificacion 3A1E.9~t
- c. The Reactiyit Marg=
recuiremrents of Specificarion 3.3.A..L are c<;conrzo:l rods -na33
/ the co<l os being
/
remoe arol1y ins erziec
/
~anI elacz--icar--
cr
\\
hydt:aul.ically d samed, cr
/have th surrounding
'-t
/
fuel assamni 5
C re-oM ed Z
- e.
A!
I=
o car roelar l
e-All oth^er csnrrtoc roc~s are fu1lly t.e~
Mae _cur :uel asSe=mblieS are remo-ec frrm t:'.e cor_ cell surround-Ig-' =esca con rzl roc or c37tro.-
roc dra.-ie rnechiLrsm to ce removed from
\\ne csre an-ocr reactsr
\\
szessel.
No fuel is loaded into the reactor core ia
=.
4.10 CORE ALTE-RATIONS (Cont)
D.
Mu.u1Hle Cont-ol Rcd Removal (Cant)
- b. The SR! c'aannels are a
operablb n
Speci-fication c.
a it arci reouirements oE Specification 3.3.A..1 are
- hydrauiay disand.o d ll control rods in
'i ar
' rrccuntoi n
each conteol r ana or -cn rods romoved o
\\
_ bec ramotmd are rullyo
~vesela the sameu~
tns are-iremsoed rms the-core ad /or ractor esaseo.
.The faur r__l=
a~semablls surrou-ndi-ng e ccb.
cz=.-c roc arzd/or cncrat l rod drive m;,zhanls 's._
is to be rema-Led -fromz.he re-ac--or
-essel ez tne same time are ramcved from th^e care amdclo-r-_ac-ar vzessel.
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