ML20030A457
| ML20030A457 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/01/1974 |
| From: | Lamley R, Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101090554 | |
| Download: ML20030A457 (8) | |
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w November 1, 1974 Directorate of Licensing Re: Docket 50-155 US Atomic Energy Commission License DPR-6 Washington, DC 20545 Big Rock Point Plant Gent,lemen:
Transmitted herewith are three (3) original and thirty-seven (37) conformed copies of a request for change to the Technical Specifications of the License DPR-6, Locket No 50-155, issued to Consumers Power Company on May 1, 1964 for the Big Rock Point Plant.
This proposed change is submitted to eliminate the minimum con-tinuous control rod withdrawal rate limit. The proposed change also re-quests Commission approval to perform a special test with the reactor suberitical to determine the maximum achievable rate of control rod with-drawal. This will provide further assurance that this maximum achievable withdrawal rate is within the rates analyzed that result in no fuel damage under the postulated start-up accident conditions.
We request that you first authorize the special test as outlined in the proposed change. After completion of this test, we vill submit the test results to confirm that the maximum achievable control rod withdrawal speeds are less than the rates assumed in the discussion of the proposed change. We believe this information vill be sufficient to allow your approval of the proposed charge.
Also attached is a change for the proposed Technical Specifica-tions submitted June 7,1974. This change deletes the 23-second with-drawal time requirement in the revised Technical Specifications currently undergoing Directorate of Licensing review.
Yours very truly, 8
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'qf Ralph B. Sewell
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CONSUMERS POWER COMPANY DOCKET NO 50-155 REQUEST FOR " CHANGE 'IO THE TECHNICAL SPECIFICATIONS LICENSE NO DPR-6 I.
For the reasons hereinafter set forth, the following change to the Technical Specifications of License No DPR-6 issued to Consumers Power Company on May 1,196h for the Big Rock Point Plant is requested:
In Paragraph 5.2.2(a)(i), delete the sentence which reads:
" Minimum withdrawal time shall be 23 seconds."
II.
Basis for Technical Specification Change In A0-2-Th dated April 3,197h and in a subsequent letter dated May 1,197h, the problems encountered with meeting the 23-second control rod withdrawal time limit were reported. A further letter dated July 19,1974 described a temporary solution, but states that the hot I
start-up accident was being reanalyzed to justify reduction of the 23-second limit. This analysis has been completed. The methods used are identical to those used in the analysis of the consequences of the rod drop accident except for the variation in rod withdrawal speed.
Those methods and assumptions were presented in Appendix A of the request for change No 27 to the Technical Specifications dated June 20,197h.
It is intended that th$ s analysis supersede the start-up accident analysis as outlined in the Big Rock Point FHSR.
The assumed core conditions are shown in Table 1, and the results of the analysis are shown in Table 2 and Figure 1.
To bracket the maximum allowable Big Rock Point in-sequence rod worth of 2 5% k, results are presented for worths of 2.0% k and 3.C% k.
The calculations were performed for the Reload G mixed oxide core loading, as this is in-tended to be the standard fuel for Big Rock Point in the future. The
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results indicate that no clad damage occurs for assumed rod withdrawal rates of less than 0.82 foot /second for a 3.0% k rod, and less than 2.25 feet /second for a 2.0% k rod. Analysis of uranium fuel is ex-pected to yield substantially the same or slightly lover values 1
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^
i e
5.
2 based on the results of the rod-drop anlysis (Figure A-3 of the above referenced report). These velocities are -believed to be much higher than the maximum achievable velocities of the Big Rock Point control rod drives.
On June 12,197h, a test was performed to measure the maximum control rod withdrawal rates with the reactor in the cold shutdotin condi-tion. Eight control rods having a history of fast withdrawal times were tested. The fastest time recorded with the rate values fully open was 16 seconds, which corresponds to an average withdrawal rate of 0 35 foot /
second. Since the accident analysis shows that a 3 0% k rod can be with-drawn at speeds up to 0.82 foot /second without fuel clad damage, it appears that there is adequate basis for removal of the 23-second time limit on rod withdrawal.
III. Request for Special Test Based on past experience with timing Big Rock Point control rods, it is possible that the maximum control rod withdrawal rate may be slightly higher at operating conditions than it is cold. Accordingly we hereby request permission to perfom a special test to verify that the maximum control rod withdrawal rate at operating temperature and pressure is less than 0.82 foot /second. Final approval of the Technical Specifications change requested herein would be attendant on the favorable results of the test, which will be submitted as an addendum to this request.
In order to perform the test, the 23-second minimum withdrawal time limit vill have to be temporarily waived, as the reactor condition during the test will be technically " power operation" as defined in Paragraph 1.2.1 of the Techni-cal Specifications. This test will also require temporary use of the jog bypass switch which we agreed to disable when the plant was above 212 F as temporary corrective action (refer to our letter dated July 19,'1974).
The reactor would be suberitical throughout the test, and it J
woulp be demonstrated before the testing of each rod that the reactor is suberitical with the rod to be tested and the highest worth remaining rod both withdrawn to the full out position.
It.is intended that the same rods would be tested as were previously tested in the cold condition to establish a trend if one exists.
The performance of this test would constitute neither an unre-viewed safety question nor a significant hazards consideration. The only accident that could conceivably occur as a result of the test would be a
i 3
series'of operator errors leading to a continuous withdrawal of a control rod which would take the reactor supercritical, ie, the start-up accident.
Using the suberiticality checks outlined above, such an occurrence would require'at least two operator errors, such as neglecting to reinsert blades after a suberiticality check, and then selecting the wrong blade to with-draw. Since reasonable precautions and overchecks will be employed during the test, the probability of such an occurrence will be at least as small as for any normal operation. There will be neither the possibility of any accident not previously analyzed, nor any reduction in safety margins as a result of the test.
IV.
Conclusions 13ased on the foregoing, both the Big Rock Point Plant Review Committee and the Sa 'ety Audit and Review Board have concluded that neither the proposed change vor the proposed special test involves a significant hazards consideration.
CONSUMERS POWER COMPANY n
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4 By
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R. A. Lamley, Vice PresTdent Date: November 1, 197h Svo.n and subscribed to before me this 1st day of November 1974.
Lei B 18all Syl'via/B. Ball, Notary Public Jackson County, Michigan My :ommission expires May 18, 1976.
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t TABLE 1 ASSUMED CORE CONDITIONS 1.
Equilibrium Fuel Cycle 2.
BOC Core Average Exposure B.43 GWD/MIM 3
Beginning of Transient Fuel Temperature 582*F k.
Moderator Temperature 582 F, 0.0 Void l
5 Beginning of Transient Power Level 240 x 10 MW 6.
Axial Exposure Distribution Exposure Exposure Zone (GWD/MTM)
Top of Core 1
h.h0 2
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11.45 6
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9 TABLE 2 MIXED OXIDE CORE KINETICS SPECIFICATIONS AND RESULTS Core: Mixed Oxide, Exxon Reload G Delayed Neutron Fraction -(i): 0.00529 Doppler Coefficient (582 F to 1200 F):
-0 960 x 10- Ak/k'F Scram Function: WIGL2 Calculation Scram Bank Velocity: 2.456 Feet /Second Scram Delay Time: 0.375 Second Rod Drop Insertion Function: WIGL2 Calculation Rod Worth (mk) 20 20 30 30 Withdrawal Rate ~(ft/second) 2.0 25 05 1.0 4
Core Average. Deposited Enthalpy (cal /gm) 47 33 52 91 25.61 h7 24 Radial Peaking Factor 1 92 1 92 2.13 2.13 Axial Peaking Factor 1 50 1.k8 1.67 1.68 Incal Peaking Factor-1.18 1.18 1.18 1.18 Peak Deposited Enthalpy (cal /gm) 161 3 177.8 107 0 199 6 e
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CORRESPONDING CHANGE 'IO THE PROPOSED TECHNICAL SPECIFICATIONS SUBMITTED JUNE 7, 197h 1.
On Page 17, delete existing Item 31.le(3)(a).
2.
On Page 18, renumber Items 3.1.1c(3)(b) and (c) 31.1c(3)(a) and (b).
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AEC DISTRIBUTION FOR PART 50 DOCKET MATERI AL (TEMPORARY FORM)
CONTROL NO:
11271 FILE:
FROM: 3g a g r g anY C
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Mr. R.B. Sewell 11-1-74 11-4-74 X
TO:
ORIG CC OTHER SENT AEC PDR XXX AEC 3' signed SENT LOCAL PDR XXX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX XXX 40 50-155 DESCRIPTION:
ENCLOSURES:
Ltr trans the following......
Proposed changes to the tech specs....
to eliminate the minimum continuous control rod withdrawal rate limit....._ l ECIE (40 cys enc 1 rec'd) n -.
PLANT NAME:
._, v n 1..
Big Rock Point
[ 23____
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