ML19339C054
| ML19339C054 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/03/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8011170276 | |
| Download: ML19339C054 (5) | |
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November 3,1980
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Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203
Dear Mr. Lundvall:
In the process of reviewing your Cycle 5 reload request dated September 22, 1980, we find that additional information as detailed in the enclosure is needed to complete our review. The additional information being requested was previously sent to Mr. J. Lippold of your staff by telecopy on October 23, 24, 29 and 31, 1980.
In order to meet the agreed upon schedule for this review, please provide the additional information by at least November 7,1980.
Sincerely, n
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Robert AI Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Request for Additional Information cc: w/ enclosure See next page 80111702M g
Baltimore Gas and Electric Company cc:
James A. Biddison, Jr.
Mr. Bernard Fowler Geheral Counsel President, Board of County G and E Building Commissioners Charles Center Prince Frederick, Maryland 20768 Baltimore, Maryland 21203 Director Technical Assessment George F. Trowbridge, Esquire Division Shaw, Pittnan, Potts and Office of Radiation Programs Trowbridge (AW-459) 1800 M Street, N.W.
U. S. Environmental Protection Agency Washington, D. C.
20036 Crystal Mali #2 Arlington, Virginia 20460 Mr. R. C. L. Olson Baltimore Gas and Electric Company U. S. Envirorrnental Protection Agency Room 922 - G and E Building Region III Office Post Office Box 1475 ATTN:
EIS COORDINATOR Baltimore, Maryland 21203 Curtis Building (Sixth Floor)
Sixth and Walnut Streets Philadelphia, Pennsylvania 19106 lan upe int t
Calvert Cliffs Nuclear Power Plant Ralph E. Architzel Baltimore Gas & Electric Company Resident Reactor Inspector Lusby, Maryland 20657 NRC Inspection and Enforcement Bechtel Power Corporation P. O. Box 437 ATTH: ifr. J. C. Judd Lusby, Maryland 20657 Chief Huclear Engineer 15740 Shady Grove Road Mr. Charles B. Brinkman Gaithersburg, flaryland 20760 Manager - Washington Nuclear Operations Combustion Engineering, Inc.
C-E Power Systems ATTN:
Mr. P. W. Kruse, Itanager Combustion Engineering, Inc.
Engineering Services 4853 Cordell Ave., Suite A-1 Post Office Box 500 Bethesda, Maryland 20014 Windsor, Connecticut 06095 Calvert County Library Prince Frederick, Maryland 20678 Director. Department of State Planninc 301 West Preston Street Baltimore, Maryland 21201 Mr. R. M. Douglass, Manager Quality Assurance Department Administrator, Power Plant Siting Program Room 923 Gas & Electric Building Energy and Coastal Zone Administration Department of Natural Resources P. O. Box 1475 Tawes State Office Building Baltimore, Maryland 21203 Annapolis, Maryland 21204 1
Enclosure REQUEST FOR ADDITIONAL-INFORMATION NO. II,
' CYCLE 5 RELOAD REVIEW CALVERT CLIFFS, UNIT NO. 1 DOCKET NO. 50-317 1.
In Section 1.0 of Appendix A, justify the statement that loss to One Steam Generator caused by a Single Main Steam Isolation Valve (MSIV) closure is the most limiting event. What other events were-analyzed?
2.
Provide a comparison of the key parameters such as DNBR, Centerline Temperature to Melt (CTM), etc., for the most limiting event with and without Reactor Protection System Asymetric Steam Generator Transient Protection Trip Function (RPS-ASGTPTF).
3.
Clarify the logic used in the equations (Figure 1)
P
- ODNB + 3 TCAL VAR-
+y TCAL = TC+KBTCAL C
Q= MAX (), B) 4.
For Table 2.2.1 of Section 9, provide the Supporting analysis for the following:
Item Functional Allowable Unit Trip Set Point Values 6.
Steam Generator Pressure - Low 1 570 psia 1 570 psia Trip Manually bypassed t 685 psia t 685 psia 9a Steam Generator Pressure Difference
- High 1 135 psid 1 135 psid 5.
It has been the practice of CE and all other PWR vendors in the past to include a calculational uncertainty in the conservative direction in determining the total available CEA worth less allowances as shown in Table 5-2.
In view of this and the requirement of Reg. Guide 1.70, Standard Format and Content of Safety Analysis Reports for
. Nuclear Power Plants, for the-presentation of required and expected shutdown margin as a function of time in cycle along with uncertainties in the shutdown margin, justify the exclusion of any calculational uncertainty in Table 5-2.
. ti. What is the change in power peaking resulting from the extension of the Cycle 4 shutdown window from 11,600. to 11,800 MWD /T7 7.
What is the magnitude of the bias that is applied to fuel _ rod power peaking values to account for the increased peaking which occurs 4
near water holes?
8.
Is our assumption correct that the ROCS code was used to compute the same safety parameters _for Cycle 5 as for Cycle 4, namely; fuel temperature coefficients, moderator temperature coefficients, boron worths, critical boron concentrations, and CEA reactivity worths?
9.
Section 15.4.7 of the Standard Review Plan for the Review of Safety Analysis Reports (NUREG-75/087) requ'res an analysis of possible fuel loading errors such as the loading of one or more fuel assemblies into improper locations. Discuss the analysis for each misloading case (including the worst case) considered and show that either the error is detectable (and thus remedial) or that the error is inconsequential and within the nuclear uncertainty or that.the offsite consequences.
of any core damage due to undetected errors are a small fraction of 10 CFR Part 100 guidelines.
- 10. A partial list of physics characteristics for Cycles 4 and 5 was presented in the Cycle 5 refueling application.
Provide a list of final Cycle 5 physics characteristics if different from the original submittal (Tables 5-1 thru 5-6) including the maximum radial power peaks expected to occur (F and F with uncertainties and biases).
7 xy 11.
(Section 7.1.2) Boron Dilution For both the Cold Shutdown and the Refueling modes (a) What is the initial boron concentration? Why is homogeneous dilution conservative?
(b) What is the minimum RCS active volume?
If this volume includes the steam generator, justify.
(c) What is the maximum dilution rate (i.e., how many pumps, the discharge of each pump)?
(d) Are the times provided in Table 7.1.2-2 calculated beginning at alarm indication? What are those alarms?
12.
(Section 7.1.6) Loss of Feedwater Flow Explain why is it concluded that no steam generator dryout occurs during a loss cf feedwater event in Cycle 5? -What is the basis for the 10 minute period discussed in this section?
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- 13. - (Section-7.1.7) Excess Heat Removal Due to Feedwater Malfunction j
This section indicates that loss of high pressure feedwater a
heaters -is equivalent to:a "small" increase in turbine demand. This-
-argument is given as a reason for the excess load event ("large" increase in turbine ' demand) to be a bounding event.
In this instance, approximately what is the' percentage increase in' turbine demand 1
that corresponds to a "small" increase'and a "large" increase?
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