ML20236S565
| ML20236S565 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/20/1998 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-06, GL-96-6, TAC-M96792, TAC-M96793, NUDOCS 9807270035 | |
| Download: ML20236S565 (25) | |
Text
{{#Wiki_filter:. \ CH ARLES II. CRUSE Baltimore Gas and Electric Cornpany Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby. Maryland 20657 l 410 495-4455 July 20,1998 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. !0-317 & 50-318 Request for Additional Information, Response to Generic Letter 96-06 LIAC Nos. M96792 and M96793)
REFERENCES:
(a) Letter from Mr. C. H. Cruse (BGE) to NRC Document Desk, dated January 28, 1997, 120-Day Response to Generic Letter 96-06,
" Assurance of Equ!pment Operability and Containment Integrity During Design-Basis Accijent Conditions" (b) Letter from Mr. C. H. Cruse (BGE) to NRC Document Desk, dated I
May2,1997, Fevision to Commitments in 120-Day Response to Generic Letter 96-06, " Assurance of Equipment Operability and l Containment In<egrity During Design-Basis Accident Conditions" (c) Letter from Mr. A. W. Dromerick (NRC) to Mr. C. H. Cruse (BGE), dated May 20, 1998, Request for Additional Information Regarding j rfg Response to Guidance [sicJ Letter (GL) 96-06 for the Calvert Clifts! fd / Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M96792 and M96793) References (a) and (b) provided Baltir.1 ore Gas and Electric Company's response to Generic Letter 96-06. Reference (c) requested adtlitional information. Baltimore Gas and Electric Company's response is contained in Attachment (1).
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9807270035 980720 PDR ADOCK 05000317-P PDR
- Document Control Desk July 20,1998 Page 2 Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, I 1 Ms ~z & CHC/EMT/ dim
Attachment:
Response to Request for Additional Information; 120-Day Response to Generic
; Letter 96-06, " Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions" -
cc: R. S. Fleishman, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident inspector,NRC S. S. Bajwa, NRC R. I. McLean, DNR
. A. W. Dromerick, NRC J. H. Walter, PSC
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ATTACHMENT (1) RESPONSE TO REQUEST FOR ADDITIONAL P;/0! NATION; 120-DAY RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS - I I l Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant July 20,1998
,, ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; 120-DAY RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" In its submittals Baltimore Gas and Electric Company (BGE) indicated that a total ofsix pipe segments in each unit were susceptible to thermally-inducedpressuri:ation. The licensee indicated that operating instructions would be changed to include draining of three of the pipe segments prior to plant operations. For two ofthe pipe segments, BGE also indicated that no overpressurization would occur due to existing installed insulation. The NRC staffrequests that BGEprovide thefollowing information: Ouestion No.1: Provide the applicable design criteria for the piping and the valves; include the required load combinations. BGE Response: As stated in our initial response to Generic Letter 96-06, each unit at Calvert Cliffs Nuclear Power Plant has six lines that were found to be susceptible to overpressurization. Three of these lines are now drained prior to returr.ing the unit to operation following outages. Two of these lines were found to meet design limits due to the presence ofinsulation that limits the peak transient temperature. One line has been insulated in a manner similar to the previous two in order to limit the peak transient temperature such that design basis limits are met. ene tion Line Description Disposition Plant Service Water 37 Operating Procedure OI-23D has been revised to require draining Refueling Pool Recycle inlet 59 Operating Procedure OI 24H has been revised to requlre draining Refueling Pool Outlet to Fuel Pool 61 Operating Procedure OI-23H has been revised to Cooling Pipe require draining Containment Plant Heating Outlet 62 Line is insulated to limit peak transient temperature. Containment Plant Heating inlet 64 Line is insulated to limit peak transient temperature. Reactor Coolant Pump (RCP) Seal IC Line has been Insulated to limit peak transient Controlled Bleed Off temperature. The applicable design loading conditions and limits are provided in Updated Final Safety Analysis Report Chapter SA, Table SA-6. I 1 I l l 1
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".. ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; 120-DAY RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" For the postulated event, Calvert Cliffs Level 3 loading conditions, Normal Operation + Pipe Rupture (Loss-of-Coolant Accident) + Safe Shutdown Earthquake, would apply. Primary membrane stress: P, & St Bending: n P1 ' P, s 4 St Cos x s2 Sg Note that for the bending limit, Pa is only M/Z and P. is intended to be PD/4t. St = Sy + 1/3 (S - Sy) The materials of the lines affected by this event are as follows: Line Description All wable Elastic Size and Material Stress (ksi) Containment Plant Heating Outlet 3" sch 40 A106 Gr B 40.9 Containment Plant Heating Inlet 3" sch 40 A106 Gr B 40.9 RCP Seal Controlled Bleed Off 3/4" sch 30 A376 TP316 40.1 Ouestion No. 2: Provide a drawing ofthe piping run between the isolation valves. Include the lengths and thicknesses of the insulation. BGE Response: The enclosed drawings are applicable to the affected lines as described below. Only the annotated sections are susceptible to overpressurization. These drawings provide requested details associated with piping lengths. Additionally, the thickness ofinsulation is listed in the table below. Unit 1 Unit 2 Line Description Insulation Thickness , Figure No. Figure No. Containment Plant Heating Outlet 1" A B Containment Plant Heating Inlet 1" A B RCP Seal Controlled Bleed Off 2" C-1 C-2 , Question No. 3: Provide the maximum calculated temperature and pressure for the pipe run. Describe in detail, the l method to calculate these pressure and temperature values. 1his should include a discussion of the heat transfer model used in the analyses and the basisfor the heat transfer coefficients used in the analyses. 2 _ _ _ _ _ _ _ _ _ _ _ _ - - _ - - - - - _ _ _ _ _J
,, ATTACHMENT (1)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; 120-DAY RESPONSE TO GENERIC LETTER 96-06, " ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS" BGE Response: Finite element models representing the various piping configurations were constructed using code ANSYS 5.2. The pipe / water models were loaded with a surface convection and bulk temperature to simulate a Loss-of Coolant Accident event. The bulk containment temperature as a function of time is obtained from the Updated Final Safety Analysis Report. The outside convective coefficient is a function of temperature, obtained from an existing containment air / steam heat transfer model previously derived from the containment analysis. The enclosed Figures D and E show the containment temperature and the convective coefficient as a function of time. The thermal conductivity of the water in each model was conservatively increased by a factor of 10 to account for mixing and additional heat flow due to convection. A thermal transient analysis was then performed that resulted in a water temperature distribution across the pipe section as a function of time. The temperatures at the pipe center and the pipe inner diameter are plotted versus time in the enclosed Figures F, G, H, and 1. Under the final design configurations (i.e., post-insulation modification), the peak temperatures and pressures are as follows: Elastic Results: Line Description Maximum Temperature Maximum Pressure Containment Plant Heating Outlet 147 F 3000 psi Containment Plant Heating inlet 147 F 3000 psi J RCP Seal Controlled Bleed Off 165*F 5410 psi Ouestion No. 4: Baltimore Gas and Electric Company also indicatelfor one segment, either a relief device would be installed or insulation would be added to the piping section exposed to loss-of-coolant accident temperature. Please clarify the specific method chosen to prevent overpressurization. IfBGE is adding insulation, please provide the same information as for the two piping segments discussed in Question No.1.
.BGE Response:
The RCP seal controlled bleed-off line was insulated to limit the peak transient temperature. No relief device was installed. The response to Question No.1 includes the relevant information for this line. l 3 L________________ _ _ _ _ _ _ _ _ _ . _ - - - -
i 1 ENCLOSURE (A) TO ATTACHMENT (1)
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DRAWINGS AND FIGURES ) l Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant July 20,1998
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Time (Seconds) ~ l Pmase64.1 psia at 177 sec.; Tmax=288'F at 71.5 sec.; Spray /CAC delay times = 70.9135.9 sec.; 2nd Spray off at 4.75 psig during post-RAS l i i-L__.________
h, 1 . . a Figure E Convective Heat Transfer Coefficient 2 ho (BTU /hr-ft -F) 500 400 300-200- ~ 100 - 0 100 150 200 250 300 CONTAINMENT AIR TEMP (F)
s Figure F Penetrations 62 and 64 without Insulatjon 1 *
"ANSYS 5.2 JAN 6 199 17:06:44 POST 26 zV =1 DIST=.75 Xr =.5
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Yr =.5 2r =.5 z-ourrER PrPE ED 960 { w 240 TEMI TEMP , j Z 226 I h1 F-g 200 j LJ ! F-
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'00 l l l 0 l 200 l 400 l l 1
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. . Figure G Penetrations 62 and 64 with 1" insulatiog 1
ANSYS 5.2 JhN 6 1997 17:10:32 POST 26 EV =1 DIST=.75 30 , xr =.5 Yr =.5 zr =.s 260 Z-BUrFER 260 m b v 247
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- Penetration IC with 2" of Insulatida, 180 160 140- -
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