ML19319C413
| ML19319C413 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/23/1978 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002140794 | |
| Download: ML19319C413 (24) | |
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MAY 2 3 1978 oar
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_q ha Docket No. 50-346 U
LICENSEE: Toledo Edison Company
SUBJECT:
TENTATIVE PROPOSAL TO AMEND OPERATING LICENSE FOR RE'40VD.
OF BURNASt.E POISON R00 ASSEMBLIES - DAVIS BESSE, UNIT NS. 1 On May 2,1978 representatives from the Toledo Edisen Company (TFJ0),
Florida Pcwer Corocration (FPC), Babcock & Wilcox Coreany (3&W).
Pickard Love & Garrick and MPR Associates met with the NRC staff to discuss TECO's plans for inspcction and possible removal of t:4e Burnable Poison Red Assemblies (GPPas) frem the reactor core of Davis Besse, Unit 1 (08-1). A list of att2ndees is provided in Eaclosure 1.
BACKGROU4D SPRAs are used to partially conteci the reactivity changes due to fuel burnup and fi;ston product buildup and augment the control provided by soluble boren and control rod assemblies. The BPRAs are dasigned tc remain in the core for the first fuel cycle only.
The BPRAs are also used to reduce the positive beginninq-of-life moderator temcentre coefficient and to flatten the radial power distribution flux.
SW described the BPPA holdown latch assembly wear oroblem which recently occurred at FPC's Crystal River, Unit 3 facility where a ceuoling broke lonse froa a BPRA and was carri,d by the reactor coolant stream to the steam generator causing damage to the tube ends orotruding frca the tute sheet of the steaa generator (see enclosure 2).
Prcblems with the latching mechanism for B&W supplied PRAs was discussed in detail at a meeting between FPC, BMI and the NRC staff cr. April 6,1973.
DISCUSSION TECO stated that based on recomendations froa 3.3, DB-1 plant coeration taas reduced to a three pump vde on April 5,1978 to reduce reactor coolant flow since DS-1 has the same designed BPPAs as CR-3 and that all 63 CPRAs would be inspected for excessive wear at a forthcoming scheduled main-tenance outage beginning "aj 5,1973 ~
TECO indicated that at the first indication of excessive wear for a given SPRA, TECO would consider removing all BPPAs from the 08-1 core to creclude the possibility of experiencing any failure of the BPRA holdown latch assem,.,
blies such as occurred at CR-3.
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NRC FORM 313 (9 76) NRCM 0240
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o 2-MAY 2 31978 TEC0 stated that the purpose of the meeting was to inform the staff of the evaluation being made by TECO and B&W to support a possible application to amend the 08-1 operating license for removing all BPRAs for the duration of the 1st fuel cycle. The application would.iustify the continued operation of the 1st fuel cycle of DB-1 at the full-rated core power of 2772 Megawatts-thermal following removal of the BPRAs from the core and the relocation of eight fuel assemblies within the core.
Also, all BPRAs removed would be replaced with orifice rod assenblies such that the core flow distribution would be identical to that of the in-place BPRAs.
B&W stated that the changes, as described above, would require control rods to be regrouped and operated differently from the 1st fuel cycle. The renoval of the BPRAs from 08-1 at a present burnup rate of 37 Effective Full Power Days (EFPD) 'would affect the power peaking, moderator temperature coefficient and soluble boron requirements. To offset the impact of BPRA removal and maintain the nuclear parameters, within the enveloce of the FSAR safety analysis, modificaticns would be i:1;lin;r,te ' for the 1s t N:i ore leading and operation.
The modifications.would include:
(1). interchanging fuel assemblies in a symmetric order, (2) changing of control red grouping ard operational sequancing of rod banks, (3) decoupling of control rod banks No. 6 and No. 7, and (4) control rod tank No. 7 would be fully inserted in the core until 145 EFPD in order to reduce the soluble toron required for critical-lity and to provide a negative temperature coef'icient at 100 pcwor opera-tion (See Enclosure 3).
TECO stated that the core physic parameters for the initial fuel cycle No. 1 and the modified cycle No. I wculd be cross-referenced in table for the DB-1 Physics Parameters and the Shutdown Mar - Calculations. Also, each FSAR accident analysis would be examined in 9ht of the BPRA removal to provide a comparison of the original and modif.ed cycle No.1 in order to insure that the initial conditions of the modified cycle No. I tranticets are enveloped by the DB-1 FSAR analysis.
TECO indicated that they have reviewed the 03-1 Techr.ical Specifications which would require changes b; sed on the modified fuel cycle No. I and that the changes would not exceed final acceptance criteria for ECCS limits (See Enclosure 4).
An outline of the planned physics startup program associated with veriff-cation of core performance for the assumptions of the safety analysis were provided (See Enclosure 5).
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NRC FORM 318 (9 76) NRCM 02 0
- u. e eoveemment casemme orwics. Seve - eae.eae
Mai 2 3 1978
. Finally, TEC0 stated that the 08-1 schedule calls for plant startup operation about May 29, 1978.
DB-1 is presently scheduled to carry a significant grid load for the CAPCO pool during the sumer peak loads and therefore TECO must have DB-1 on line for power creration about the middle of June. TECO stated they would keep the staff informed on the inspection of the BPRAs and possible pending application for amend-ment to the OL for 08-1.
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Leon Engle, Project Manager Light Water Reactors Braa.ch No.1 Division of Project Management
Enclosures:
1.
Attendance List 2.
BPRA Latchdown Mechanism 3.
Modified Fuel Cycle 1 4.
Technical Specification Revisions 5.
Startup Program cc: See page 4 i
1 LWRIf'd-rf LW m LEngle/ red}
JSt b 5/C/78 5/p78 xac roam n mo xacx o2.o
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MAY 2 31978 4
cc: Toledo Edison Company ATTN: Mr. Lowell E. Roe Vice President, Facilities Development Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Mr. Donald H. Hauser, Esq.
The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Gerald Charnoff, Esq.
Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Leslie Henry, Esq.
Fuller, Seney, Henry and Hodge 300 Madison Avenue Toledo, Ohio 43604
ENCLOSURE 1 ATTENDANCE LIST FOR MEETING HELD ON MAY 2, 1978 WITH THE TOLEDO EDISON COMPANY DAVIS BESSE. UNIT NO. 2 DOCKET NO. 50-346 NUCLEAR REGULATORY COMMISSION TOLED0 EDISON COMPANY W. Brooks J. Buck M. Chatterton C. Domeck F. Coffman G. Hurrell J. Creswell J. Lingenfelter L. Engle F. Miller D. Fieno T. Murray G. Mazetis E. Novak M. McCoy R. Sund J. McGough J. Menning H. Molen FICKARD LOWE & GARRICK J. Rajan H. Richings T. Robbins R. Riggs R. Seyfrit H. Silver BABCCCK & WILCOX COMPANY J. Stolz T. Tambling R. Berchin M. Tokar R. DeMans S. Weiss M. Gudorf E. Kane D. Mors FLORIDA POWER CORPORATION MPR ASSOCIATES Q. DyBois S. Weems
ENCLOSURE Y ~
BPRA LATCHDOWN MECHANISM
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ENCLOSURE 4 TECHNICAL SPECIFICATION REVISIONS SecTION SUBJECT 3.1.2.8 BORATED WATER SOURCES - SHUTDOWN - L.C.0 3.1.2.9 BORATED WATER SOURCES - OPERATING - L.C.0.
FIGURE 3.1-1, MIN. BORIC ACID TAMK CONTAINED VOLUME VS CONC.
3.1.3.5 REGULATING ROD INSERTION LIMITS - L.C.0.
FIGURE 3.1-2, REG. ROD GROUP INSERTION LIMITS FOR 4 - PUMP OPERATION FIGURE 3.1-3, REG. ROD GROUP INSERTION LIMITS 1
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FIGURE 3.1-4 CONTROL ROD CORE LOCATION AND GROUP ASSIGNMENTS FIGURE 3.1-5 CONTROL ROD CORE LOCATION Af1D GROUP ASSIGNMENTS 3.2.1 AXIAL POWER IMBALANCE - L.C.0 FIGUR E 3.2-1, AxI AL POWER IMBALANCE ENVELOPE FOR 4 - PUMP OPERATION 3
FIGURE 3.2-2, AXIAL POWER IMBALANCE ENVELOPE FOR 3-PUMP OPeaATION FIGURE 3.2-3, AXI AL POWER IMBALANCE ENVELOPE F0P. 2-PUMP OPERATION (DELETED) 4.1.1.1.2 REACTIVITY 3ALANCE NORMALIZATION 5.35 DESIGN FEATURES, REACTOR CORE, FUEL ASSEMBLIES
' ENCLOSURE 5
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SUMMARY
Docket File-NRC PDR Local PDR TIC NRR Reading LWR #1 File E. Case R. Boyd R. DeYoung D. Vassallo J. Stolz K. Kniel
- 0. Parr S. Varga L. Crocker D. Crutchfield F. Williams R. Mattson H. Denton D. Muller Project Manager:
Attorney, ELD E. Hylton IE (3 )
ACRS (16)
L. Dreher S. Rubenstein NRC
Participants:
4