ML20024G289
| ML20024G289 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/29/1977 |
| From: | Wachter L NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G287 | List: |
| References | |
| A00L-770729, AL-770729, NUDOCS 9102080488 | |
| Download: ML20024G289 (9) | |
Text
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UNITED STATES NUCLEAR REGUIATORY COMMISSION NORTRERN SIATES POWER COMPANY MCETICELLO NUCLEAR GENERATING PIANT Docket No. 50 263 REQUEST FOR AMENItiENI TO OPERATING LICENSE NO. DPR. 22 j
(License Amendment Request Dated July 29, 1977)
Northem States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Dthibit B.
Exhibit A describes the proposed changes alonE with reasons for the change.
Exhibit B is a set of Technical Specification pages incorporating the proposed changes.
This request contains no restricted or other defense infomation, t
4 NORDIERN STATES POWER COMPANY l
By O
o w. M /
C L J kachter I
Vice President, Power Production &
System Operation
%4 On this 29th day of July 1977, before me a notary public in and for said County, personally appeared L J Wachter, Vice President, Power Production 6 System Operation, and first being duly sworn i
acknowledged that he is authorized to execute this document in behalf of Northern States Power Company, that he knows the contents thereof and that to i
the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
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DENISE E. HALVORSON h NOT AM PutuC
- WINNEsOTa HENNEPIN COUNTY Wy Commisaaon tipites On 10,1ssi ;
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EXHIBIT A MONTICELLO NUCLEAR CENERATING PIANT DOCKET No. 50-263 LICENSE AMENINENT REQUEST DATED JULY 29, 1977 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS APPENDIX A OP PROVISIONAL OPERATING LICENSE NO. DPR-22 Pursuant to 10CFR50.59, the holders of Provisional Operating License DPR-22 hereby propose the following changes to the Appendix A Technical Specifications:
1.
_ ROD WORTH MINIMIZER PROPOSED CHANGES On Page 78 TS 3.3.B.S and 4.3.B.5, change the acronym "RWM" to "RBM".
REASON FOR CHANGE A change to this page was requested in our License Amendment Request Dated September 22, 1972. On November 27, 1973 that change was issued.
In the course of re-typing the page this error crept in.
There is no question but what it should read RBM as shown in our September 22, 1972 submittal and all prior versions; the staff safety evaluation did not address this as an additional intended change when it was issued.
The wording proposed above is consistent with the remainder i
of those specifications and their bases, whereas the present wording is note SAFETY EVALUATION This change merely corrects a previous typing error and has no safety significance.
2.
MCPR LIMITS PROPOSED CHANGF1 On Page 189D, TS 3.11.C and on Page 189F, first paragraph of Bases 3.11.p,,f the operating MCPR limits from "1.38" to "1.46" and from "1.29" to "1.37 change or 8x8 and 7x7 fuel respectively.
RFASON FOR CHANGE License Event Report M-RO-77-12 identified a delta MCPR of 0.08 which was found necessary and administrative 1y applied at that time.
It was discovered that a model change was appropriate to properly reprecent the manner in which the load shedding of the recirculation pumps occurred during the limiting abnormal operational transient, r
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EX111 BIT A 2
I SAFETY EVAIDATION The Monticello Plant electrical protection design scheme incorporates trip circuitry for the recirculation pump M-G set drive motors. This is done to avoid the transfer of large, non-essential electrical loads from the auxiliary trans-former to the reserve transfomer in the event of a turbine or generator trip.
D e pump trip uses devic $ having a long history of reliable operation with I
certain elements of re/
ancy; however, it does not meet the same rigorous standards as does the ri 3r protection system. When fuel thermal limits were analyzed using the llenc' y heat flux correlation, it was found that limiting a
transients were not affe m d by the recirculation pump trip. Transier.ts were analyzed assuming the pump trip existed.
An analysis for conditions expected at the end of the next cycle was recently donc using the same model as in the past except that GETAB replaced the llench-Levy j
correlation. We results of a turbine trip without bypass shwed a delta CPR 1
for the pump trip case 0.08 s.aaller than the case without the trip.
In evaluating this unexpected situation, it was discovered that in the past the pump trip was I
modeled to occur too rapidly. The appropriate corrections, referenced to measured l
plant data, were incorporated into the model. ne modified trancient model was used for analysis of the next cycle. An adjustment of 0.08 to the MCPR operating limit is bounding for the duration of the present cycle. A re-analysis of the transient shows that the recirculation pump trip occurs too late to have any effect in detemining thermal limits. Turbine and generator trips will continue to be modeled to include the pump trip to best represent the existing equipment.
The MCPR operating limit is derived by aiding to the MCPR safety limit the maxie mum delta CPR of the limiting abnomal opecational transient. We reactor transients and the themal hydraulic respons(s were analyzed as described in the topical report, "GE/IMR Generic Reload Licensia Application for 8x8 Fuel, Revision 1, Supplement 4, April 1976, NEDO-20360',
It was found that at the I
end of the next cycle the turbine trip without bypass, event and tne generator load rejection without bypass event are equally limiting, having a delta CPR of 0.40 for 8x8 fuel. (All 7x7 fuel will be removed from the core during the next refueling outage.) The ICPR safety limit of 1.06 is not changed, placing the I
new !CPR operating limit at 1.46 We input and output for the limiting tran-I sient calculations are presented in the attached Tables 1, 2 and 3 and Figures 1, 2 and 3.
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I Table 1 GETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMCTERS i'
Peaking factors (local, radial and axial) 1.22/1.49/1.40 R-Factor 1.094 i
Bundle Power (HWt) 5.004 Nonfuel Power Fraction 0.035 6
Core Flow (1b/hr) 57.6 x 10 4
Bundle Flow (1b/hr) 1.07 x 105 i
Reactor Pressure (psia) 1030 1
Inlet Enthalpy (Btu /lb) 523.2 Initial MCPR 1.47 i
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Table 2 TRANSIENT INPtrI PARAMETERS Thermal Pever, (MWt) 1670 100%
0 Rated Steam Flow, (ib/hr) 6.78 x 10 1007.
l Rated Core Flow, (1b/hr) 57.6 x 106 1007.
Dome Pressure, (psig) 1025 Turbine Pressure, (psig) 980 S/RV Setpoint, (psig) 1080 + 1%
S/RV Capacity (at Setpoint),
6/68.76 (No. /7.)
S/RV Time Delay, (msec) 400 S/RV Stroke Timne, (msec) 100 Void Coefficient, (c /7.Rg)
-8.92 l
Void Fraction, (7.)
37.47 i
Doppler coefficient, (c/ F)
-0.217 1
Average Fuel Temperature, (OF) 1192 l
Scram Reactivity Curve Figure 1 Scram Worth, ($)
-30.71 Table 3 TRANSIENT DATA
SUMMARY
Core Peak Peak Peak Peak f
Power Flow 9
Q/A P
P Transient (7.)
(7.)
,G1 (7.)
(pkg)
(DEip.) @
l Generator Load 100 100 468.3 123.7 1193 1223 0.40 Rejection w/o N
Bypass Turbine trip 100 100 444.5 122.8 1193 1222 0.40 w/o Bypass m
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SCR AM RE ACTIVITY v$ TIME CONTROL ROD DRIVE V8 TIME O.s7s cRD IN PERCENT
O. SCRAM cvRve usto iN Analysis 90 y
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Scram Reactivity and Control Rod Drive Specifications, 4
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EXHIBIT B LICENSE kiENDMENT RMUEST DATED JULY 29, 1977 This exhibit consists of the following pages revised to incorporate all of the proposed Technical Specification changes:
18 189D
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189F
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