ML20151Z266
| ML20151Z266 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/07/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151Z269 | List: |
| References | |
| NUDOCS 8602140115 | |
| Download: ML20151Z266 (2) | |
Text
r gmgp Electric & Gas Company n. Na o
g ug g g M 18 Nuc2ar operations
-SCE&G namc--
February 7, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPP-12 Technical Specification Change
Dear Mr. Denton:
In a letter dated November 8,1985, from Mr. D. A. Nauman to Mr. H.
R. Denton, South Carolina Electric and Gas Company (SCE&O) transmitted WCAP 10814, " Analysis of Capsule
'U' from the South Carolina Electric and Gas Company Virgil C. Summer Unit 1 Reactor Vessel Radiation Surveillance Program," for the NRC Staff's review.
As a result of the completion of SCE&G's own internal review of the document, the proposed changes to the Technical Specifications found in Attachment A to this letter are requested.
These changes to section 3/4.4.9, " Pressure / Temperature Limits - Reactor Coolant System," and its bases are de* ribed in the following paragraphs.
The withdrawal schedule for the reactor vessel specimen capsules is found in Table 4.4-5 of the Technical Specifications.
The current schedule calls for one capsule to be removed at first refueling (completed as described in WCAP 10814), followed by one at each of 6, 10 and 15 Effective Full Power Years (EPPY) with the two remaining designated as standby capsules.
SCE&G is requesting this schedule be changed to allow for the removal of a capsule during each of the 3rd, 5th, 10th and 17th refueling outages, leaving one capsule as a standby.
This refueling outage schedule, based on currently projected fuel cycles, corresponds approximately with the 3, 6,12 and 20 EPPY of operation schedule as recommended by Westinghouse in Section 7 of WCAP 10814.
The proposed change also b
revises which capsules will be removed at each scheduled surveillance.
This change is to provide for the removal of those capsules with greatest lead factors early in plant life.
The O
corrections to the lead factors resulted from revised and updated c
methodologies used to calculate these values.
This revised O
schedule will provide additional data early in plant life to help determine long term trends of the reactor vessel material O<t g
properties due to the effects of radiation.
~~
%:.o A cML gooI vso w s.
Mr. Harold R. Denton Technical ~ Specification Change February 7, 1986 Page 2 The results of the examination of the first specimen have indicated that Figures 3.4-2 and 3.4-3 of the heatup and cooldown rates require revisions.
The revision to Figure 3.4-2 includes updated pressure-temperature and criticality limitations for 100'F/hr heatup rates and establishes these limitations for 50*F/hr heatup rates.
Revised Figure 3.4-3 is very similar to the figure currently found in the Technical Specifications except for the discontinuity between 110'F and 130'F affecting the 25 'and 50 degree per hour curves.
This discontinuity is necessary in order to comply with the May 17, 1983 amendment to 10 CFR 50, Appendix G.
Appendix G requires, "when pressure exceeds 20 percent of the preservice system hydrostatic test pressure, the temperature of the closure flange regions that a're highly stressed by the bolt preload must exceed the reference temperature of the material in those regions by at least 120*F for normal operation."
Appendix A of WCAP 10814 provides a complete discussion of the bases for the i
revised Figures 3.4-2 and 3.4-3 Please note the administrative deletion of the reference to. Figure 3.4-4 on page 3/4.4-29 of the Technical Specifications.
This change is requested since currently no Figure 3.4-4 exists.
The revisions to the Bases section are to provide support for the proposed changes to section 3/4.4.9 of the Technical Specifications 4
and are consistent with the information contained in WCAP 10814.
Attachment B to this letter is SCE&G's no significant hazards determination.
The schedule for submittal of this proposed change was discussed and agreed upon with the Project Manager.
These changes to the Technical Specifications have been reviewed and' approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee.
Please find enclosed the application fee of $150.00 required by 10 CFR 170.
If you should have any questions, please advise.
6 y tr ly 7 urs, i
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AMM/ DAN:dwf Enclosures (3)
I pc:
V. C. Summer C. L. Ligon (NSRC)
O. W. Dixon, Jr./T. C. Nichols, Jr.
K. E. Nodland E. H. Crews, Jr.
R. A. Stough j
E. C. Roberts G. O. Percival J. G. Connelly, Jr.
R. L.
Prevatte l
W. A. Williams, Jr.
J. B. Knotts, Jr.
J. Nelson Grace H. G. Shealy Group Managers NPCF
- 0. S. Bradham File l
C. A.
Price 1
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