ML17201M311
| ML17201M311 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/27/1989 |
| From: | Siegel B Office of Nuclear Reactor Regulation |
| To: | Bliss H COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17201M313 | List: |
| References | |
| TAC-69235, NUDOCS 8902010212 | |
| Download: ML17201M311 (3) | |
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January 27, 1989 Docket No.: 50-237 DISTRIBUTION Mr. Henry*E. Bl1ss Nuclear Licensing ~anager Commonwea 1th Edi-son Compa~y Post Office Box 767 Chicago, Illlno1s 60690 :,.
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Dear Mr. Bli.ss:
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NRC &_Local PDRs ufcfr i<et-f-i-le--2 PDIII-2 GHolahan Lluther OGC ACRS (10)
EJordan BG rimes BSiegel MVirgil io GHolah_an
SUBJECT:
.. DRESDEN.N'UGLE-AR POWER STATION. UNIT 2 -**c(ARIFICATIONS TO AMENDMENT NO. 104 SAFETY 'EVALUATJON':{SE}.:.(TAC NO. 69235).
By lett~r dat.~d January,r,:*::" 1989:: Am~~qr_n~'nt,No. 104 to Provisiona*l Operating License NO.
QP*R~19.forDresden~U~it 2-.wa$.,-issue*o~
Biased on a January 17, 1989*
conference caJ 1. D,etween J*. S ilady Q~ CE Co and B. ?. i ege l of th_e NRC, it was determined~lha~t~6 cl~rificatiOn$ t6 the ~E-w~re needed to insure that it was properly *interpreted *.. These were 'iden~ified *in.your.letter dated January 19, 1989.
One clarification is related to the fuel bundle types to. be utilized
. in Dresden 2 Cycle 12.
In the staff's SE, only the two new bundle types that.
have not been previously evaluated were addressed.
The third bundle type, *
- which is identical to XN-3L.type loaded in Dresden 2 Cycle 11, was previously
-approved by the. staff. for use in Cycle 11 and therefore was not addressed in the SE.
The other~cl~rffication is related to Single Rod Sequericing (SRS) control. strategy~ CThe* wording in the SE is such that a relationship.between the *sRS. control strategy and the control.rod withdrawal error calCulation* is implied.
The staff agrees with CECo that operation in.th~ SRS mod~ is not
- required to assure that the control rod withdrawal error }s not limitihg.
In addition, duripg 'the January 17, 1989 conference call,' six minor typo-graphical errors were identified. Three of these, which were not related to the amendmeQt reque~t, are the res~lt of transferring the.Dresden-Technical
_Specifications to our word processing system~ The corrected pages have been.
- included as entlosu~es to this letter.
8902010212. 890127 i.\\:.-..
PDR ADOCK 05000237~.
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Enclosures:
As.stated cc w/enclosures:.
.. See next page PDIII-2 d*
BSiegel;f" 1/J.7 /89 sincere/s /.*.
- Byron Siege 1, Proj,ect Manager Project Directorate III-2 Division of Reactor Projects
- III, IV, V-and Special Projects PDIII-2}!£ DMu 11 er -;:i, 1/ '],? /89
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No.: 50-237 Mr. Henry E. Bliss Nuclear Licensing Manager Co1rn11onwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Bliss:
January 27, 1989
SUBJECT:
DRESDEN NUCLEAR POWER STATION UNIT 2 - CLARIFICATIONS TO AMENDMENT NO. 104 SAFETY EVALUATION (SE) (TAC NO. 69235)
By letter dated January 6, 1989, Amendment No. 104 to Provisional Operating License NO. DPR-19 for Dresden Unit 2 was issued.
Based on a January 17, 1989 conference call between J. Silady of CECo and B. Siegel of the NRC, it was determined that two clarifications to the SE were needed to insure that it was properly interpreted. These were identified in your letter dated January 19, 1989.
One clarification is related to the fuel bundle types to be utilized in Dresden 2 Cycle 12.
In the staff's SE, only the two new bundle types that have not been previously evaluated were addressed.
The third bundle type, which is identical to XN-3L type loaded in Dresden 2 Cycle 11, was previously approved by the staff for use in Cycle 11 and therefore was not addressed in the SE.
The other clarification is related to Single Rod Sequencing {SRS) control strategy. The wording in the SE is such that a relationship between the SRS control strategy and the control rod withdrawal error calculation is implied.
The staff agrees with CECo that operation in the SRS mode is not required to assure that the control rod withdrawal error is not limiting.
In addition, during the January 17, 1989 conference call, six minor typo-graphical errors were identified. Three of these, which were not*related to the amendment request, are the result of transferring the Dresden Technical Specifications to our word processing system.
The corrected pages have been included as enclosures to this letter.
Enclosures:
As stated cc w/enclosures:
See next page Sincerely, f: S~~roject Manager Project Directorate Ill-2 Division of Reactor Projects - Ill, IV, V and Special Projects
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- Mr. Henry E. Bliss Commonwealth Edison Company cc:
Michael I. Miller, Esq.
Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mr. J. Eenigenburg Plant Superintendent Dresden Nuclear Power Station Rural Route Ill Morris, Illinois 60450 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 Mr. Michael E~ Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Dresden Nuclear Power Station Units 2 and 3