ML20237D329
| ML20237D329 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 12/17/1987 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20237D331 | List: |
| References | |
| NLS-87-270, NUDOCS 8712230201 | |
| Download: ML20237D329 (2) | |
Text
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4-J
-.u P. O. Box 1551
- Raleigh, N. C. 27602 DEC 17 56T SERIAL:
NLS-87-270 LYNN W. EURY 10CFR50.90 Senior Vke President operations support 85TSB18 United States Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT j
REACTOR VESSEL MATERIAL SURVEILLANCE WITHDRAWAL SCHEDULE 1
1 Gentlemen:
j On March 5, 1986, Carolina Power & Light Company (CP&L) submitted a request for a license amendment for the Brunswick Steam
)
Electric Plant (BSEP), Unit Nos. 1 and 2.
The proposed change to
(
Technical Specification (TS) Table 4.4.6.1.3-1 for both units revises the reactor vessel material surveillance withdrawal i
schedule.
During recent discussions, your Staff suggested a more flexible method for establishing the surveillance withdrawal schedule.
Specifically, the Staff suggested that the withdrawal schedule i
for the second and third surveillance capsules be based on the evaluation results of the first capsule rather than basing the withdrawal schedule on specific exposures determined by engineering calculations.
Since the capsule exposures are estimated to lag the maximum reactor vessel fluence, withdrawal of the capsules based on the current schedule may not yield a sufficiently_ informative shift in the transition temperature.
T h'e p r o p o s e d c h a n g e, as stated in our initial March 5, 1986 submittal, is intended to maximize the data obtained from the surveillance capsule withdrawal schedule based on three available capsules per unit.
The Staff suggested schedule specifies removal of the first capsule for BSEP-1 after approximately 8 effective full power j
years (EFPY) and removal of the first capsule for BSEP-2 after approximately 10 EFPY.
The removal schedule for the second and third capsules would then be established based on an evaluation of the results of the first capsules from each unit.
The Company agrees with the Staff that this approach would provide the most effective means of establishing the withdrawal schedule for the second and third capsules for each unit.
hpol 8712230201 871217 DR ADOCK 05000 4
Document Control Desk NLS-87-270 / Page 2 The Company has evaluated the revised surveillance withdrawal schedule against the significant hazards analysis submitted with the initial TS change request.
The revised schedule enhances the previously submitted schedule since it provides the mechanism for assuring the maximization of data from reactor vessel surveillance specimens.
Based on this evaluation, CP&L has determined that the conclusions of the significant hazards analysis are still valid; therefore, the modification of the initially submitted surveillance withdrawal schedule does not involve a significant hazard consideration.
Enclosed are the revised TS Tables 4.4.6.1.3-1 for BSEP-1 and BSEP-2.
Please refer questions regarding this matter to Mr. Sherwood R.
Zimmerman at (919) 836-6242.
Yours very truly, L.
W.
Eur EKN/ekn (RVMSWS1)
Enclosures:
1.
Unit 1 proposed Technical Specification page 2.
Unit 2 proposed Technical Specification page cc:
Dr.
J.
Nelson Grace Mr.
W.
H. Ruland Mr.
E.
D.
Sylvester Mr. Dayne H. Brown L. W. Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.
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