ML19296D238
| ML19296D238 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/12/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19296D239 | List: |
| References | |
| NUDOCS 8003030058 | |
| Download: ML19296D238 (7) | |
Text
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'o UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION g
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WASHINGTON. D. C. 20555 o
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICtLLO NUCLEAR GENERATING PLANT, UNIT N0. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 43 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated September 17, 1979, as supplemented by letters dated November 1, November 30.
and December 31, 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Provisional Operating License No. DPR-22 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 43, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0
s Ip o, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications
'Date of Issuance:
FI5RUMY *. 2 ISE3
ATTACHMENT TO LIC!."SE AMENDMENT NO. 43 PROVISIONAL OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 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 area of change.
Remove Insert 29 29 1890 189D
'89E 189E 109G 189G O
m
3.0 LIttiTIf4G CotiDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS B.
Upon discovery that the requirements for the B.
Once per day during power operation the number of operable or operating trip systems MFl.PD (Maximum Fraction of Limiting or instrument channels are not satisfied, Power Density) shall be checked and the action shall be initiated to:
scram setting given by the equation in Specification 2.3.A shall be adjusted if 1.
Satisfy the minimum requirements by necessary.
placing appropriate devices, channels, or trip systems in the tripped condition, or 2.
Place and maintain the plant under the specified required conditions using normal operating procedures 29 3.1/4.1 REV Amendment tio.
43
3.0 LIMITING CONDITIONS FOR OPERATIori 4.0 SURVELLLANCE REQUIREMENTS C.
Ifinimum Critical Power Ratio (HCPR)
C.
Minimum Critical Power Ratio (ifCPR) 1.
During power operation, the Operating HCPR HCPR shall be determined daily during Limit shall be 1 1 41 for 8x8 f uel,1 1.41 for reactor power operation at 3,25% rated 8x8R fuel, 1 1 44 for P8x8R fuel at rated power thermal power and following any change and flow.
If at any time during operation it in power level or distribution which is determined that the limiting value for HCPR has the potential of bringing the core is being exceeded, action shall be initiated to its operating MCPR limit.
within 15 minutes to restore operation to within the prescribed limits. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits. If the steady state MCPR 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 />.
For core flows other than rated the Operating HCPR Limit shall be the above applicable HCPR value times K where K is as shown in Figure 3.11.3. g g
2.
If the gross radioactivity release rate of noble gases at the steam jet air ejector monitors exceeds, for a period greater than 15 minutes, the equivalent of 236,000 uC1/sec following a 30-minute decay, the Operating MCPR Limits specified in 3.II.C.I shall be adjusted to 11.42 for 8x8 f uel, 21.46 for 8x8R f uel and 11.46 for P8x8R f uel, t.imes the appropriate K. Subsequent operation with the adju,ted HCPR values shall be s
per paragraph 3.ll.C.I.
1890 3.!!/4.11 REV Amendment flo.
43
TABLE 3.11.1 ffAXIMUtl AVERAGE PIANAR LINEAR llEAT GENERATION RATE vs. EXPOSUh Exposure MAPI.llGR FOR EACil FUEL TYPE (kw/f t)
IND/STU 811B262 8DB250 8DB2191.
8DRB265/P8DRB265 8DRB282/P8DRB282 200 10.6 10.6 10.7 10.4 10.3 1,000 10.7 10.7 10.7 10.4 10.4 5,000 10.7 10.7 10.8 10.4 10.4 10,000 10.8 10.8 10.7 10.5 10.5 15,000 10.7 10.7 10.7 10.5 10.5 20,000 10.7 10.6 10.6 10.4 10.4 25,000 10.6 10.6 10.6 10.3 10.3 30,000 10.6 10.6 10.2 10.3 10 3 35,000 9.8 40,000 8.9 45,000 8.O*
- For extended buruup program test bundles 189E 3.11/4.11 REV Amendment fl0. 43
nasen Continned C.
tilnimum Critical Power Ratio (HCPR)
The I:CCS cvaluation presented in Ref erence 4 assumed the steady state ifCPR prior to the postulated los s-o f-c oo la nt accident to be 1 18 for all f uel types.
In addittoa. the ECCS analysis presented in Reienence 6 assumed an initial liCPR of 1.24 for reduced flow conditinns. The Operating HCPR Limit is determined from the analysis of transients discussed in Bases Sections 2.1 and 2.3.
By maintaining l
an operating MCPR above these limits, the Safety Limit (T.S. 2.1.A) is maintained in the event of the most limiting abnormal operational transient.
For operation with less than rated core flow the Operating HCPR Limit is adjusted by multiplying the above limit by K.
Reference 5 discusses how the transient analysis done at rated conditions the reduced flow situation when the proper K factor is applied.
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encompasses Since the tioble gas activity levels above that stated in 3.II.C.1 are indicative of fuel f ailure.
be positively identified, a more conservative Operating HCPR Limit must be applied failure mode cannot to account for a possible f uel loading error.
Thuse abnormat operational transients, analyzed in FSAR Section 14.5, which result in an automatic reactor sc ram a re 'not considered a violation of the LCO.
Exceeding HCPR limits in such cases need not be reported.
Amendmentflos.)
, 43 189c 3 11-BASES