ML20024G284
| ML20024G284 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/04/1975 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20024G285 | List: |
| References | |
| NUDOCS 9102080482 | |
| Download: ML20024G284 (5) | |
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/ A August 4, 1975 j
Y Mr. D. L. Ziemann, Chief N)Qg G/D +
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Operating Reactors Branch # 2
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U. S. Nuclear Regulatory Commission
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Washington, DC 20555 R-
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Dear Mr. Ziemann:
MONTICELLO NUCLEAR GENERATING P1 ANT Docket No. 50-263 License No. DPR-22 1.icense Amendment Request Dated August 4.1975 This letter is to supplement our July 9, 1975 response to your letters concerning ECCS analyses.
On December 27, 1974, you sent to us an Order for Modification of License for the Monticello Nuclear Generating Plant, which requested reanalyses of the Monticello ECCS perfomance and submittal of appropriate proposed Technical Specification changes by July 9, 1975, using revised criteria.
On April 24, 1975, you expanded the above analyses to include certain considerations for manually controlled, electrically operated valves. Your June 18, 1975 letter identified additional required information for ECCS analyses.
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Our July 9,1975 letter provided the ECCS analyses as received f rom our reactor s
vendor without our review. We have now had the opportunity to review the analyses, evaluate confomance to the above documents and prepare the appropriate Technical Specification change requeet.
The ECCS analyses which are the bases for the Tech-nical Specification change are attached as Exhibit C of this submittal.
It is essentially the same as that subtritted on July 9,1975, with the exception of minor corrections thrcughout the report and insertion of non-proprietary versions of the proprietary figures.
We believe that we have complied with your April 24, 1975 letter in full.
We have reviewed the ECCS analyses submitted July 9, 1975, and i
have connunicated with General Electric, who perfomed the analyses, to detemine the extent to which that evaluation complies with the 'kequired infomation" identi-fiud by your June 18, 1975 letter.
Five areas warranting further discussion are is follows (Item numbers correspond to those in the June 18, 1975 letter):
Item III The analyses only investigate a loss of coolant accident initiated during operation with both recirculation pumps; single loop flow is no*. specif3cally analyzed.
We are presently discussing with General Electric their capabi-lities and scheduling for providing this aspect of the analyses.
It should be noted that partial loop operation is provided primarily for times of forced maintenance.
The l
likelihood of the LOCA event simultaneous with partial loop f^(3 operation is ver/ remote.
9102080482 750804 DR ADOCK 05000263 PDn
s i 'i N
HERN OTATEC POWER MPANY D. L. Ziemann 2
Auru<t 4, 1975 Item IV.A The Thermal Power vs Time Plot is not included in the Monticello lead plant analysis (Quad-Cities) and is there-fore included widi this letter as Attachment A.
Item IV.B Curves of Hot _ Pin Internal Pressure, Hot Spot Pellet Average Temperature, and Core Outlet Flow vs Time have not been submitted. We understand that General Electric will supply these curves for BWR/4 and 6 lead plants by October 17, 1975 and that they have your concurrence that completion of the analyses by that date will not delay the review and action on the Appendix K Analyses for any plant.
Item IV.D The identifying run dates etc., are not on curves and tabulations in the Monticello ECCS analyses. Attachment B is a tabulation of le; numbers which provides traceability of the model used for each plot provided in the July 9,1975 Monticello ECCS analyses.
i Item IV.E The Time to Rupture is not included with other re-questedidentification marks on figures and tabulations. Gene ral Electric contends that this information is not meaningful by it-self and that 8 x 8 fuel does not perforate.
The analytical results using the ECCS model modified in accordance with the Dec-ember 27, 1974 Order are somewhat different than reported in the past.
One such result, the maximum average planar linear heat generation rate (MAPLHGR) curves are part of Technical Specification and are, therefore, the subject mat-ter of this License Amendment Request.
This otherwise simple change is comp-11cated by the fact that it affects previously requested changes which have not been acted on so far.
Exhibit A. explains how the curreat Technbal Specifications and previously requested Technical Specification changes are affected.
Exhibit B provides printed pages having been corrected to include the proposed changes.
You will find that tie proposed Technical Specification changes include a M.\\PLHM curve for the 8D219 fuel type which is not currently used in the Monticello re-actor. As discussed in our July 24, 1975 letter to Mr. K. R. Goller, we plan to insert that fuel type during a refueling outage scheduled to comnence Septem-ber 12, 1975.
The SD219 fuel type is a standard BWR fuel assembly which is of essentially the same mechanical and nuclear design as fuel currently in use at Monticello with the excepticn that it has lower enrichment than the otha r fuel types. The ECCS model handles ecch fuel type in the same manner but because of fuel parameters (such as enrichment) the resulting MAPLHGR curves are unique to each fuel type. This change merely implements the calculated results for all fuel types.
This is the only Technical Specificad on change required for in-sertion of the 8D219 fuel type.
We wish to emphasize the need for prompt action on these changes.
The evaluation of tm nsiente ivr the reload core is being done based on the GEIAL concept.
We l
request that in addition to the attached proposed Technical Specification changes, our GETAB License Amendment Request (Dated March 12, 1975) be implemented prior to our September 12, 1975 outare. We also request that action be taken on the I
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NOQTHERN OTATED POWER LJMPANY O
Mr. D. L. Ziemann 3
August 4, 197; parts of our License Amendment Request (Dated August 20, 1974) which are still applicabic. At the present time we are rest ricted by the legal operating listits identified in your December 27, 1974 Order which do not appear in the Monticello Technical Specification.
We believe it is iraprudent to operate for an extended period of time under this arrangement. We request that a single ret of MAPLHGR curves be issued for Technical Specifications and that other peripheral require-ments be eliminated as soon as possible.
We stand ready to be of assistance to you in this effort.
Yours very truly, h"
W' L. O. Mayer, PE Manager, Nuclear Support Se rvice s Lm/MHV/ deb cc:
J. G. Keppler G. Charnof f MPCA Attn:
J. W.
Terman MECCA Attn:
H.
J.
Vogel City of St. Paul Attn:
D.
L.
Ficker S. J. Cadler
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ATTAO TJ,T.\\
Normali:cd Core Power Vs. m e Time, Sec Nomali:ed power 0.
1.00000 0.10 0.98351 0.20 0.92606 0.40 0.74519 0.60 0.59272 0.80 0.49796 1.00 0.34641 2.00 0.16634 3.00 0.10617 4.00 0.08676 5.00 0.07811 6.00 0.07462 7.00 0.07254 8.00 0.06996 9.00 0.06796 10.00 0.06604 20.00 0.05820 30.00 0.05459 40.00 0.0509S 50.00 0.04902 60.00 0.04705 70.00 0.04564
-Y 80.00 0.04449 90.00 0.04358 100.00 0.04267 150.00 0.03928 200.00 0.03588 250.00 0.03465 300.00 0.03342 350.00 0.03218 400.00 0.03095 450.00 0.03020 500.00 0.02945 600.00 0.02795 700.00 0.02700 800.00 0.02604 900.00 0.02533 1000.00 0.02463 2000.00 0.020S9 3000.00 0.01893 4
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O Attachment B ECCS Figure Log Numbers Figure Log Number Date A-la SLOS5 6/13/75 A-id SLO 56 6/20/75 A-2a SLOSS 6/13/75 A-2d SLOS6 6/20/75 A-3a 5 LOSS 6/13/75 A-3d SLOS6 6/20/75 B-la-1 ST054 6/13/75 B-la-2 ST055 6/9/75 B-1d ST096 6/20/75 B-2a SC203 6/17/75 B-2d SC203 6/24/75 C-la-1 5H087, 5S056 6/17/75 C-la-2 5H087, 5S066 6/17/75 C-ld-1 5H087, 55066 6/20/75 C-1d-2 5H087, 55066 6/20/75 C-2a-1 5H087, 5S066 6/17/75 C-2a-2 5H087 6/17/75 C-2b-1 5H088, 55065 6/17/75 C-2b-2
- 5H088, 6/17/75 D-la SC203 6/17/75 D-id SC203 6/24/75 D-2a SH087 6/17/75 D-2b 5H088 6/17/75 D-3 5H087, SH088 6/17/75 D-4A/5A SC205 6/19/75 D-4B/5B SC204 6/19/75 D-4C/5C SC203 6/19/75 D-4D/50 SC202 6/19/75 D-4E/5E SC201 6/19/75
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