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- MEMORANDUM F0'R: C chwenc+r Chief, Operating Reactors Branch-1, 00R D. Ziemann, Chief, Operating Reactors Branch-2, D0R FROM:
R. Baer, Chief, Reactor Safety.Branen, D0R
SUBJECT:
REVIEW 0F SINGLE LOOP OPERATION IN BWR'S There are four current technical assistance requests dealing with the review of the acceptability of operaticn of BWR's with a recirculation loop.
The requests and the plants are:
TACS Number Plant None Pilgrim-1 293 6170 Brunswick-2 '314 6190 Monticello 163 6184 Dresden 2/3 and 139e Di Quad Cities 1/2
- 2. 6 4, 2 (., 5 This memorandum is being written to discuss the status of these reviews.
Each of these reviews consists of several major aspects; namely, ECCS performance, normal operation, and transients.
The Analysis Branch (AB) of DSS is reviewing the ECCS model and the Reactor Safety Branch (RS) of DDR is reviewing the plant specific aspects for both normal operation and ECCS performance.
The approach agreed upon by the General Electric Company, AB and RS was as follows:
(1) General Electric would submit a topical report documenting the ECCS mcdel used for single loop BWR operation.
(2) The Reactor Safety Branch would review the information submitted on Pilorim 1 and request any additional information required regarding methods of calculations for normal operation and transients.
(3) General Electric would update the Pilgrim 1_ do_cket to reflect item (2).
(4)
The Pilorim 1 docket would be referenced for future submittals,
and r'esponses to questions on non-fCCf'Ealculational methods for
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plants under current review would also reference the Pilgrim 1 docket.
8406070145 C40319 PDR FOIA BELL 84-105 PDR.
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. Unfortunately, the General Electric rcenmy hge sljppe_d,the schedule for the documentation of the model that we require.
Their latest scheduled submittal date is early in 1977 Mr. Leonard Olshan of the RS has been assigned to review the plant specific portion of.information submitted by the licensee.
He is currently performing item 2 above.
We expect to have any requests for additianal information on Pilorim i submitted to the Project Manager by November 16, 1976.
Requests for additional information on the other dockets will be transmitted to the appropriate project managers _by December 3. 1976. As indicated in item 4, above, responses to any such request for information may reference the Pilgrim 1 docket regarding methods' of calculation for normal operations.
The Reactor Safety Branch of D0R and the Analysis Branch of DSS expect to jointly issue an SER on Pilgrim 1 on December 15, 1976.
It should o
be noteo Inat this SER will require the submittal of a topical report on the ECCS model for singl5 loop operation before such operation will be authorized.
The schedule for the SER on the other dockets will be determined joir.tly by the appropriate Operating Reactors Branch, the AB and the RS, once responses from GI have been received, and a firm date for the ECCS topical report has been determined.
f,,.1[x R. /W m Robert L. Baer, Chief Reactor Safety Branch Division of Operating Reactors cc:
V. Stello D. Eisenhut Z. Rosztoczy P. O'Connor C. Trammell R. Snaider R. Frahm L. Olshan F. Coffman R. Woods S. Weiss C. Berlinger
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' LOP 228, Rev. 1
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INITIAL NO SIGNIFICANT FAZARDS CONSIDERATION DETERMINATION
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AND NOTICING ACTION Docket No.
50-263 Facili ty: Monticello Licenses:
Northern States Power Co.
Date of appl'ication: 7/2/82 as supplemented on 10/0/82 Request for:
l (See attached.)
. Initial Determination:
(
) Procosed determination - ame,dment request involves no significant hazards considerations (NSHC).
( x ) liial determination - amendment request involves significant hazards cc.nsioerations (SHC).
Basis for Determination
(
) Licensee's NSHC discussion has been reviewed and is accepted.
See attached amendment request.
- X ) Basis for this determination is presented in the attached.)
(
) 0ther (state):
e (Attach additional sheets as needed.)
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Initial Noticina Action:
(Attach appropriate notice or input for monthly FRN) 4 1.
(
) Monthly FRM. Notice, of opportunity for hearing (30 days) and request for comments on proposed NSHC determination - monthly FRN input is attached (Attachment 8).*
2.
(
) Individual FRN (30 days).
Same notice matter as above.
Time does not
'3 allow waiting for next monthly FRN (Attachments 9a and 9b).
(THIS FORM SHOULD SE TYPED EXCEPT FOR UMUSUAL, URGENT CIRCUMSTANCES.)
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Request for:
The amendment would change the Technical Specifications to incorporate revised safety and operating limits associated with the operation of Monticello Nuclear Generating Plant with one recirculation loop out of serv-The changes proposed by the licensee would provide for reduced Average ice.
an in-Power Range Monitor (APRM) flux scram trip and rod block settings, crease in the safety limit Minimum Critical Power Ratio (MCPR) value and revisions to the allowable Maximum Average Planar Linear Heat Generation Rate Presently,
-(MAPLHGR) values suitable for use with an idle recirculation loop.
the Monticello Technical Specifications would require plant shutdown if an The idle recirculation loop cannot be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
amendment would authorize the plant to operate up to 50% of rated power for extended periods of time. Supporting the amendment request, is a report pre-pared by General Electric that presents the analysis for core performance, in accordance with the licensee's application for amendment dated July 2, 1982 as supplemented on October 5,1982.
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a Basis for:
[The Commission has provided guidance for the application of the standards for determining whether a significant hazards consideration exists by providing examples of amendments that are considered not likely to involve significant hazards consideration (48 FR 14870). One such amendment involves a relief granted upon demonstration of acceptable operation from an operating restric-3 tion that was imposed because acceptable operation was not yet demonstrated.
This assumes that the operating restriction and the criteria to be applied to a reouest for relief have been established in a prior review and that it is justified in a satisfactory way that the criteria have been met.
The Monticello Technical Specifications presently require plant shutdown if an idle recirculation loop cannot be returned to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This restriction was imposed because insufficient information existed to enable the staff to establish criteria for operation with an idle recircula-tion loop. Although such criteria have since been established, and analyses have indicated that it should be safe to operate Boiling Water Reactors (BWRs) i on a single loop in the range of 851 power, operating experience with an i
idle recirculation loop at Browns Ferry 1 (BF-1) in late 1979 raised concerns about authorizing single loop operation for BWRs. When the Tennessee Valley Authority (TVA) tried to increase power at BF-1 above about 59% of rated i
power, while operating on a single loop, unexpected variations in jet pump flow, neutron flux, and related parameters were noted. Neither the causes i
i nor the potential effects of these variations have been determined or reviewed by the staff for operation with a single recirculation loop. Thus, it has not l
been justified in a satisfactory way that the criteria for operation with a single loop have been met. The application for amendment involves changes which do not satisfy the criteria of the applicable example of an amendment l
whicii.ould likely be found not to involve significant hazards consideration.
Therefore, the staff has made a determination that the application for l
amendment may involve a significant hazards consideration.
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