ML19354E124
| ML19354E124 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/16/1990 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-89-003, IEB-89-3, NUDOCS 9001250441 | |
| Download: ML19354E124 (3) | |
Text
e A
f BALTIMORE l
OAS AND ELECTRIC CHARLES CENTER P.O. BOX 1476. BALTIMORE, MARYLAND 21203 ocomot c. cacci.
January 16, 1990 Vict Patsiot=1
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U. S. Nuclear Regulatory Commission Washington, DC 20$$$
ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & $0-318 Resnonse to NRC Bulletin No. 89-03
REFERENCES:
(a) NRC Bulletin No. 89-03; Potential Locs of Required Shutdown Margin During Refueling Operations, dated November 21, 1989 (b) Letter from Mr. G. C. Creel (BG&E) to Document Control Desk (NRC), dated March 15, 1989; 10 CFR Part 21 Written Report:
Nuclear Fuel - Potential Loss of Shutdown Margin Gentlemen:
The Nuclear Regulatory Commission (NRC) Bulletin concerning potential loss of required shutdown margin during refueling operations (Reference a) was a result of a 10 CFR Part 21 notification submitted by Baltimone Gas and Electric Company (BG&E)
(Reference b). Since the potential problem was identified BG&E has taken actions to prevent the occurrence of the conditions described in the Bulletin. Our response to the three action items presented in Reference (a) is as follows.
1)
Assure that any intermediate fuel assembly configuration (including control rods) 7 intended to be used during refueling is identified and evaluated to maintain sufficient refueling boron concentration to result in a minimum shutdown margin of approximately SE h
The final core configuration is analyzed to ensure that the required shutdown margin exists at the minimum allowable boron concentration. A map is prepared showing the h-infinity of each assembly in each location in the final configuration.
Any intermediate move which places an assemb'y in a core location other than. Its final core location or the core location from which it was just removed must be preceded by a comparison of the transiting assembly's k-infinity with the k-infinity of the assembly which will finally reside in that location. Only assemblies with k-infinities equal to or less than the k-infinity of the assembly which will finally reside in that location are allowed to be temporarily placed into that location. This ensures that adequate shutdown margin exists at all times during the refueling process.
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9001250441 900116 PDR ADOCK 05000317 Q
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Doe:me:t Contr:1 Desk January 16, 1990 Page 2 2)
Assure that fuel loading procedures only allow those intermediate fuel assembly configurations that do not violate the allowable shutdown margin and that these procedures are strictly adhered to.
The core refueling procedure, Fil-6, implements the controls described above. All changes to the fuel movement sequence must be checked, as applicable, against the k-infinity map to ensure that intermediate core configurations do not compromise the required shutdown margin. The procedure is stamped ' Compliance Mandatory,' requiring strict procedure adherence.
3)
Assure that the staff responsible for refueling operations is trained in the procedures recommended in Item 2 above and understand the potential consequences of violating these procedures. This training should include the fundamental aspects of criticality control with higher enriched fuel assemblics.
Fil-6 requires that the Operations staff involved in refueling activities attend a shift briefing presented by the Nuclear Engineering Unit Shift Engineers prior to each refueling.
Additionally, all Nuclear Engineering Unit Shift Engineers attend a
procedure training session prior to each refueling, The briefing and training cover all major aspects of the procedure, emphasizing precautions and potential safety concerns, The steps to be taken to prevent challenging the required shutdown margin, including discussions of criticality control, are included in this briefing.
These actions ensure that the required shutdown margin is maintained at all times during refueling operations at Calvert Cliffs Units I and 2.
Should you have any further questions regarding this matter, we will be pleased to discuss them with you, i
Dog: ment CItrol Desk January 16, 1990 Page 3 Very truly yours, STATE OF MARYLAND TO WIT
- fna dii (d $8lDe k I hereb ce tify that on the //r day of AM4AAF,19 efore m, the sugeriber,O'/a Notary Public of the State of hWyland in arg for hh2 La M
, personally appeared George C. Creel, being dtily sw'orn, and states that he is face President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said Corporation.
WITNESS my lland and Notarial Scal:
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(ftar[l'ublic My Commission Expires:
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/f fO O ""f GCC/BDM/bjd cc:
D. A. Brune, Esquire
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J. E. Silberg, Esquire R. A.Capra, NRC l
S. A.McNeil,NRC 1
W. T. Russell, NRC j
J. E. Beall, NRC l
T. Magette, DNR
)
i
- ______j
t Refueline Information Recueu r
' 1.-
Name of facility o
i h
Haddam Neck i
2.
Scheduled date for next refueling shutdown.
May 15,1991 t
3.
Scheduled date for restart following refueling.
April 28,1990 l
4.
(a)
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
t Yes (b)
If answer is yes, what,in general, will these be?
l Incorporate the guidance provided in the NRC Generic 1.etter 88 16. The Generic l.etter addresses removing cycle specific parameters from Technical Specifications and t
transferring them to the technical report supporting cycle operation.
(c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any umeviewed safety questions are associated with the core reload?
l (Ref.10 CFR section 50.59)
('
n/a (d)
If no such review has taken place, when is it scheduled?
n/a 5.
Scheduled date(s) for submitting proposed licensing action and supporting inLmation.
The TSCR was submitted to the NRC on July 28,1989.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design l
or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
No 7.
The number of fuel assemblies (a)in the core and (b) in the spent fuel storage pool.
(a) 0 (b) 858 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
h 1168
(,,
9.
The projected date of the 1,ast refueling that can be discharged to the spent fuel pool assuming the present heensed capacity.
1996 r
.__