ML20206R814
| ML20206R814 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/17/1986 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20206R794 | List: |
| References | |
| NUDOCS 8609190206 | |
| Download: ML20206R814 (7) | |
Text
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Revised Technical Specifications for Cycle 11 Reload Revised Pages: 210 J
212f 214b 217 Use of barrier fuel at Cooper Nuclear Station (CNS) was approved in Amendment l
No. 93 to the facility -operating license (FOL) issued June 3, 1985.
This amendment revised Technical Specifications to include the application of barrier fuel to the figures of Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure and Minimum Critical Power Ratio (MCPR) versus T (based on tested measured scram time). Amendment No. 94 to the'CNS FOL permitted single loop operation and provided for the detection and suppression of thermal-hydraulic instabilities during both dual loop and single loop operation. One of the conditions specified in Amendment No. 94 for. single loop operation was a reduction in the MAPLHGR curves (Figure 3.11-1) by various factors depending on the fuel type. A ' reduction factor for barrier fuel (BP8x8R) was not included. This proposed change to the CNS Technical Specifications includes a reduction factor for barrier fuel.
which is an addition to page 210 in Section 3.11.A.
The reduction factor of
-0.77 was obtained from General Electric and is the same for 8x8R and P8x8R fuel.
Three additional changes are requested to Technical Specifications regarding the reload.
A.
On page 214b, add to the bases of Section 3.11, Reference No. 9 that defines r used in Figure 3.11-2.
This reference was previously in Technical Specifications but was inadvertently deleted by Amendment No. 94.
B.
On page 217, under Section 5.2.A., add BP8x8R to the list of fuel assemblies that make up the core.
C.-
On page 212f, Figure 3.11-2e is changed as a result of the reload analysis.
The Supplemental Reload Licensing Submittal for Cooper Nuclear Station for Cycle 'll is attached to support your review.
Evaluation of this Proposed Change with Respect to 10CFR50.92 A.
The enclosed Technical Specification change is judged to involve no i
significant hazards based on the following:
1.
Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Evaluation Use of barrier type fuel (BP8DRB283) at CNS was reviewed and approved in Amendment No. 93 to the CNS FOL.
The remaining fuel types were previously loaded in the core and are standard General Electric reload designs described in the latest approved version of GESTAR II (NEDE 24011-A).
8609190206 860917 PDR ADOCK 05000298 P
PDR-
1 A cycle specific rod ' drop accident analysis performed for both hot and cold shutdown cases shows that the maximum peak enthalpy reached is 244 calories per gram, below the NRC criterion of 280 calories
~'
per gram..
Amendment ' No. 94 to the FOL incorporated into CNS Technical.
Specification GE Service Information Letter (SIL)-380 operat.ng recommendations. Reference No. I states that plants whose Technical
' Specifications enforce the recommendations of GE SIL-380 need not perform cycle specific stability calculations for reloads.
Subsequently, no stability analysis was performed in the Attachment.
Reference No. 2 states that operating limits consistent with the ~
recommendations of GE SIL-380 demonstrate compliance with General
' Design Criteria'Nos. 10 and 12 for cores loaded with approved fuel designs.
From the above, the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?
Evaluation As stated before, barrier fuel and the other fuel contained in the core have been reviewed and approved by the NRC Staff for use in other BWR's and at CNS in Amendment No. 93.
The possibility of a new or different kind of accident from any previously evaluated has already been considered.
3.
Does the proposed amendment involve a significant reduction in a margin of safety?
Evaluation The reload analysis used a MCPR Safety Limit of 1.07 which is consistent with Technical Specification 1.1.A.
'Section 10
" Core-Wide Transient Analysis Results " of the attachment, gives a maximum pressure increase of approximately 160 psi for the Load Rejection without Bypass Transient. Added to a maximum operating pressure of 1,045, gives a resultant pressure of 1
1,205 psi which is below the peak dome pressure limit of 1,337 psig -
in Technical Specification 1.2.1. and below the 1,240 psig safety valve setpoint per Technical Specification 2.2.1.C.
The reactivity margin of Technical Specification 4.3.A.1 is met, as t
is the 3.0 percent ak suberitical condition for 600 ppm Stand-By Liquid Control Shutdown capability.
With the above, and the operating limit MCPR bounding the events discussed in the Attachment, the proposed amendment does not involve a significant reduction in a margin of safety.
i l
l
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.)
7 Section.13, "Overpressurization Analysis Summary", gives a maximum vessel pressure of 1,250 psig upon MSIV closure with attendant failure of the MSIV position switch scram and failure of one safety / relief valve. This is less than the 110 percent of design pressure (1,375 psig) critaria discussed in Technical Specification 1.2, Bases.
B.
Additional basis for proposed no significant hazards consideration determination:
The Commission has provided guidance concerning the application of the
. standards for determining whether a significant hazards consideration exists by providing certain examples (48CFR14870). The examples include:
"(111) For a nuclear power reactor, a change resulting from a nuclear reactor core reloading, if no fuel assemblies significantly different from those found previously acceptable to the NRC for a previous core at the facility in question are involved. This assumes that no significant changes are made to the acceptance criteria for the Technical Specifications,. that the analytica' methods used to demonstrate conformance with the Technical Specifications and regulations are not significantly charged, and that NRC has previously found such methods -
acceptable."
IU
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- LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.11-FUEL RODS 4.11-FUEL RODS
- Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements apply associated with the fuel-rods apply to to the parameters which monitor the those parameters which monitor the fuel fuel rod operating conditions.
rod operating conditions.
Objective Objective The Objective of the Limiting Condi-The Objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type performance of the fuel rods, and frequency of surveillance to be Specifications applied to the fuel rods.
A.
Average Planar Linear Heat Specifications Generation Rate (APLHGR)
During steady state power opera-A. -
Average Planar Linear Heat tion, the APLHGR for each type of Generation Rate (APLHGR) fuel as a function of average planar exposure shall not exceed The APLHGR for each type of fuel the limiting value shown in Figure as a function of average planar 3.11-1 for two recirculation loop exposure shall be determined operation. For single-loop oper.
daily during reactor operation ation the values in these curves at 3 25% rated thermal power.
are reduced by 0.84 for 7x7 fuel; 0.86 for 8x8 fuel; 0.77 for 8x8R, l
P8x8R, and BP8x8R fuel. If at any time during steady state operation it is determined by normal surveillance that the limiting value for APLHGR is being exceeded action shall be initiated within 15 minutes to rescore operation'to within the prescribed limits.
If the APLHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corres-ponding action shall continue until the prescribed limits are again being met.
B.
Linear Heat Generation Rate (LHGR)~
B.
Linear Heat Generation Rate (LHGR)
The LHGR as a function of core During steady state power opera-height shall be checked daily tion, the linear heat generation during reactor operation at 1 25%
rate (LHGR) of any rod in any fuel rated thermal power, assembly at any axial location shall not exceed the maximum allow-able LHGR as calculated by the following equation:
" max 5 LHGRd [1 - {(AP/P)(L/LT) LHGR - Design LHGR = G KW/ft. d (AP/P) max
- Maximum power spiking penalty =
N -210-
3.11' Bases: (Cont'd) The K factor curves shown in Figure 3.11-3 were developed generically g which are applicable to all BWR/2, BWR/3, and BWR/4 reactors. The K factorswerederivedusingtheflowcontrollinecorrespondingtoraked thermal power at rated core flow as described in Reference 1. The K, factors shown in Figure 3.11-3, are conservative for Cooper opera-tion Because the operating limit MCPR's are greater than the original 1.20 operating limit MCPR used for the generic derivation of K. g References for Bases 3.11 l '. - Licensing Topical Report, General Electric Boiling Water Reactor, Generic Reload Fuel Application, (NEDE-24011-P), (most current approved submittal). 2. " Supplemental Reload Licensing Submittal for Cooper Nuclear Station Unit 1," (applicable reload document). 3-8. Deleted l 9. Letter (with attachment), R. H. Buckholz (GE) to P. S. Check (NRC), " Response to NRC Request for Information on ODYN Computer Model," September 5, 1980. -214b-
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- L ;.. _
O.0 0.2 0.4 0.6 0.8 1.0 T ( based on teslui measured scrom time os defined in Reference 9) Figwe 3.11-2e P8x8R S BP8 x 8R Fuel (BOC to EOC-1000 mwd /ST) 1 l 212 f l
00 '. k.,, -- a 5.0 MAJOR DESIGN FEATURES 5.1 Site Features The Cooper Nuclear Station site is located in Nemaha County, Nebraska, on the west bank of the Missouri River, at river mile 532.5. This part of the river is referred to by the Corps of Engineers as the Lower Brownv111e Bend. Site coordinates are approximately 40* 21' north latitude and 95* 38' west longitude. The site consists of 1351 acres of land owned by Nebraska Public Power' District. About 205 acres of this property is located in Atchison County, Missouri, opposite the Nebraska portion of the station site. The land area upon which the station is constructed is crossed by the Miaerari River on the east and is bounded by privately owned property on the north, south, and west. At the west site boundary, a county road and Burlington Northern Railroad spur pass the site. The reactor (center line) is located approximately 3600 feet from the nearest property boundary. No part of the present property shall be sold or leased by the-applicant which would reduce the minimum distance from the reactor to the nearest site boundary to less than 3600 feet without prior NRC approval. The protected area is formed by a seven foot chain link fence which surrounds the site buildings. 5.2 Reactor A. The core shall consist of not more than 548 fuel assemblies in any combination of 7x7 (49 fuel rods) and 8x8 (63 fuel rods) and 8x8R/P8x8R/BP8x8R (62 fuel rods). l B. The core shall contain 137 cruciform-shaped control rods. The control material shall be boron carbide' powder (B C) compacted to approximately 4 70% theoretical density, except for the Hybrid I control rods which contain approximately 15% hafnium. 5.3 Reactor Vessel The reactor vessel shall be as described in Section IV-20 of the SAR. The applicable design shall be as described in this section of the SAR. 5.4 Containment A. The principal design parameters for the primary containment shall be as given in Table V-2-1 of the SAR. The applicable design shall be as des-cribed in Section XII-2.3 of the SAR. B. The secondary containment shall be as described in Section V-3.0 of the
- SAR, C.
Penetrations to the primary containment and piping passing through such -217-w- )}}