ML20206G602
| ML20206G602 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/30/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G606 | List: |
| References | |
| NUDOCS 8704150060 | |
| Download: ML20206G602 (7) | |
Text
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UNITED STATES o
8 NUCLEAR REGULATORY COMMISSION o
g WASMNGTON, D. C. 20555
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIDGIL C. SUMMER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendnent No. 60 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission1 has found that:
A.
The application for amendnent by South Carolina Electric & Gas Company and South Carolina Public Service Authority (the licensees) dated June 27, 1986, as supplemented November 21, 1986, and February 25, 1987, complies with the standards and reovirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules l,
and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application.
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (il that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
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(2) Technical Specifications j
The Technical Specifications contained in Appendix A, as revised through Amendment No. 60
, are herehv incorporated in the license.
l The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective as of its date of issuance, and shall be implemented within 30 days of issuance.
I FOR THE NUCLEAR REGillATORY COMMISSION
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a.a Lester. Rubenstein, Director PWR Project Directorate #2 l
Division of PWR Licensing-A j
Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical q,
Specifications Date of Issuance: March 30, 1987 I
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4 ATTACHMENT TO LICENSE AMENDMENT 1
AMENDMENT NO. 60 TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages Insert Pages I
3/4 2-8 3/4 2-8 3/4 2-10 3/4 2-10 B3/4 2-5 B3/4 2-5 1
l 1
4 I
i l
i
MEASUREMENT UNCERTAINTIES OF 2.1I FOR FLOW l
AND 4.0% FOR INCORE MEASUREMENT OF Fj ARE INCLUDED.lN THIS FIGURE 38 34 ACCEPTABLE UNACCEPTABLE OPERATION REGION OPE, RATION REGION 4
34 t::
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e (1.00,29.47) o., gp (1.00,29.17) m f g*, ',
5 SEE NOTE P
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(1.00,28.29) 28 (1.00,27.99) i i
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26 24 0.90 0.95 1.00 1.05 1.10 i
i R = Fj/1.49 [1.0 + 0.211.0. P3 FIGURE 3.2 3 RCS TOTAL FLOW RATE VS. R THREE LOOP OPEft'ATION l
NOTE: Wh.a op.retlag la thi. reglen. the teettistes powee 8.vol..h.H b.
s.n.is.r.4 to n soow.: e.i.4 tn rm.i
..,inre: e t rigur. 2.t.t.
SUMMER - UNIT 1 3/4 2-10 Amendment No. H, 60_,
4 POWER DISTRIBUTION LIMITS i
3/4.2.3 RCSFLOWRATEANDNUCLEARENTHALPYRISEHOTCNANNELFACTOR LIMITING CONDITION FOR OPERATION i
3.2.3 The combination of indicated Reactor Coo'iant System (RCS) total' flow rate and R shall be maintained within the region of allowable' operation shown on Figure 3.2-3 for 3 loop operation.
l, Where:
F5H 5'
R = 1.49 [1.0 + 0.2 (1.0 - P)]
a.
I THERMAL POWER b.
P
=
Fh=MeasuredvaluesofFhobtainedbyusingthemovableincore c.
detectors to obtain a power distribution map.
The measured I
valuesofFhshallbeusedtocalculateRsinceFigure3.2-3 i
includes measurement uncertainties of 2.1% for flow and 4% for j
incoremeasurementofFh,and APPLICABILITY: MODE 1.
' L~
ACTION:
i With the combination of RCS total flow rate and R outside the region of accept-l able operation shown on Figure 3.2-3:
i a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
]
l i
1.
Restore the combination of RCS total flow rate and R to within the above limits, or i
2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High trip setpoint to l
1ess than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially beir.g outside the above limits, verify j
through incore flux mapping and RCS total flow rate comparison that i
the combination of R and RCS total flow rate are restored to within i
the above limits, or reduce THERMAL POWER to less than 5% of RATED L_..-
THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through incore flux i
mapping and RCS total flow rate comparison, to be within the region of acceptable operation shown on Figure 3.2-3 prior to exceeding the l
following THERMAL POWER levels:
1 SUMER - UNIT 1 3/4 2-8 Amendment No. M,60
6 POWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) i F,y limit for Rated Thermal Power (F,RTP) as provided in the Radial Peaking Factor Limit Report per specification 6.9.1.11 was determined from expected power control maneuvers over the full range of burnup conditions in the core.
[
WhenRCSflowrateandFharemeasured,noadditionalallowancesare necessary prior to comparison with the limits of Figures 3.2-3.
Measurement errorsof2.1%forRCStotalflowrateand4%forFhhavebeenallowedfor h
in determining the limits of Figure 3.2-3.
1 The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of indicated RCS flow is sufficient to i
detect only flow degradation which could lead to operation outside the acceptable region of operation shown on Figure 3.2-3.
3/4.2.4 QUADRANT POWER TILT RATIO I
The quadrant power tilt ratio limit assures that the radial power j
distribution satisfies the design values used in tha power capability analysis.
Radial power distribution measurements are made during startup
- i testing and periodically during power operation.
1 The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x y plane power tilts.
A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in j
F is depleted.
The limit of 1.02 was selected to provide an allowance for q
l the uncertainty associated with the indicated power tilt.
4 The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and cor-rection of a dropped or misaligned control rod.
In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by q
reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.
4, i
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable the movable incore detectors are used to confim that i
the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.
The incore detector monitoring is done with a full incore flux map or two sets of 4 symmetric thimbles.
These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.
l 3/4.2.5 DNS PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the nomal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent SupMER - UNIT 1 8 3/4 2-5 Amendnent No. 0,56. 60
3 POWER DISTRIBUTION LIMIT BASES I
HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their
}
limits following load changes and other expected transient operation.
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SUMMER - UNIT 1 B 3/4 2-6 Amendment No. 56
.