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Forwards Revised FSAR Pages Responding to SER Confirmatory Items 14,16 & 17 Re Containment Isolation Valve Data & Containment Purge Sys from 830525 Meeting in Bethesda,Md
	ML20024A449
Person / Time
Site:	Catawba
Issue date:	06/07/1983
From:	Tucker H; DUKE POWER CO.
To:	Adensam E, Harold Denton; Office of Nuclear Reactor Regulation
References
	NUDOCS 8306170316
	Download: ML20024A449 (15)
	v • d • e

. . - - - - -

DuxE POWER GOMPAhT P.O. HOX 33180 CifAHLOTTE, N.C. 28242 HALB. TUCKER TELEPHONE vu.E PREmmRNT (704) 373-4531

.mu . ..o==== June 7, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

On May 25, 1983 representatives from Duke Power Company and the NRC/ Containment Systems Branch met at the NRC's offices in Bethesda, Maryland to discuss certain Confirmatory Items identified in the Catawba Safety Evaluation Report.

The attached Catawba FSAR pages have been revised to respond to Confirmatory Items 14, 16 and 17. These pages will be included in Revision 8 to the FSAR.

Very truly yours,

)

Hal B. Tucker

/A W Wf ROS/php Attachment cc: (w/ attachment)

Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq.

Attorney-at-Law P. O. Box 12097

Charleston, South Carolina 29412

\

cP 0306170316 830607 O ,) l PDR ADOCK 05000413 PDR E

c.

Mr. Harold R. Denton, Director June 7 1983 Page 2 cc: (w/ attachment)

Palmetto Alliance 2135 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Elley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207

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O

_w TABLE 6.2.4-1 (Page 9)

Containment Isolation Valve and Actuation Data NOTES:

1. Valve arrangements are shown in Figure 6.2.4-1.

2. Definition of Actuation Signals 5 - Safety Injection Signal (T signal also activated by S signal)

T - Containment Isolation Signal (Phase A containment isolation)

P - Containment High-High Pressure Signal (Phase B containment isolation)

3. Deleted

4. Symbols:

Valve Position Abbreviations 0 Open C Closed A Automatic R Remote Operation M Manual Local Operation LC Locked Closed C/0 Closed prior to Sump or Hot Leg Recirculation; Open after Sump or Hot Leg Recirculation LO Locked Open AI Fails As is Actuator Type l

E Motor (Power Source - Electricity)

. D Pneumatic Diaphragm (Power Source - Compressed Air) ,

l P Pneumatic Piston (Power Source - Compressed Air) l l HW Handwheel (Power Source - Manual)

5. Each Personnel Lock will have double doors with an interlocking system to prevent both doors being opened simultaneously.

6. System Identification from valve number.

BB - Steam Generator Blowdown System l BW - Steam Generator Wet Layup Recirculation System l CA - Auxiliary Feedwater System CF - Feedwater System FW - Refueling Water System KC - Component Cooling System KF - Spent Fuel Cooling System i NB - Boron Recycle System Rev. 8 l

l

TABLE 6.2.4-1 (Page 10)

Containment Isolation Valve and Actuator Data NC - Reactor Coolant System ND - Residual Heat Removal System NF - Ice Condenser System NI - Safety Injection System NM - Nuclear Sampling System NS - Containment Spray System NV - Chemical and Volume Control System RF - Fire Protection System RN - Nuclear Service Water System SA - Main Steam to Auxiliary Equipment SM - Main Steam System SV - Main Steam Vent to Atmosphere VB - Breathing Air System

~

VE - Annulus Ventilation System VI - Instrument Air System VP - Containment Purge System VQ - Containment Air Release and Addition System VS - Station Air System VV - Containment Hydrogen Sample and Purge System VX - Containment Air Return Exchange and Hydrogen Skimmer System WE - Equipment Decontamination System WG - Waste Gas System WL - Liquid Radwaste System YM - Demineralized Water System

7. The given response indicates whether or not the penetration is con-nected to Seismic Category 1 equipment inside and/or outside contain-ment.

8. The Containment pressure control isolation valves are also automat-

. ically closed by high containment radiation.

9. Connected Piping is temporary and is removed before startup. Pene-trations are closed with blind flanges during all modes containment integrity is required. A Type B Test will be performed on these penetrations per 10CFR50, Appendix J.

10. See FSAR Section 6.3 for automatic actuation signals for these valves.

11. See Section 6.3 for Accumulator Water level signal used to close these valves after initial injection.

12. Open for startup, closed when plant reaches ' 30% power.

13. As documented in Engineering Justification Report SES-JR-10, the one inch containment isolation valves for this system were purchased as Duke Class F instead of Duke Class B. This was necessary due to the high system design pressure (8000 psig) which exceeded the pressure / temperature ratings of the ASME section III Code.

Rev. 8

%b TABLE 6.2.4-1 (Page 11)

Containment Isolation Valve and Actuator Data

14. Valve closes upon receipt of a high radiation signal.

15. The following systems are considered Engineered Safety Feature systems:

FW - Refueling Water System NB - Boron Recycle System NC - Reactor Coolant System ND - Residual Heat Removal System NF - Ice Condenser System NI - Safety Injection System NS - Containment Spray System NV - Chemical and Volume Control System VE - Annulus Ventilation System

16. Power Source - Refer to Note 4.

17. General Design Criteria met -

Any valve arrangement designated with an "A" or "B" prefix meets the spec-ifications of GDC 55 and 56 of 10CFR50, Appendix A. Valve arrangements with a "D" prefix meet GDC 57.

Valve arrangements with a "C" prefix fall into a miscellaneous category in which the piping is considered a part of the containment and meeting GDC 50. In addition, the 'C2' arrangement (the fuel transfer tube) also meets GDC 51, 52, and 53 (see Section 6.2.4.2.1). 'C1' and 'C3' arrange-ments are considered closed to outside atmosphere. See Note 9 concerning specifics on arrangement 'C3'.

18. All potential bypass leakage paths in dual containment plants are required

, a Type C test per Position No. 7, Section B, of Branch Technical Position CSB 6-3, " Determination of Bypass Leakage Paths In Dual Containment Plants."

19. Piping, isolation valves, and actuators in the Containment Isolation System outside Containment are located inside a Seismic Category 1 enclosure com-plex, and are located as close as practical to the Containment wall; i.e.,

in almost all cases, isolation valves will be located immediately after the penetration assembly. There will, however, be exceptions, such as the case of the main steam lines which require a series of safety valves before the isolation valve. Also, there will be some exceptions due to normal struc-tural design arrangements. Actual lengths of pipe from penetrations to the isolation valves outside Containment have been kept to a minimum.

20. Deleted

21. Deleted Rev. 8

m %

TABLE 6.2.4-1 (Page 12)

Containment Isolation Valve and Actuator Data

22. During the injection phase of safety injection, these valves are closed.

Water from the refueling water storage tank (FWST) provides approximately 48 feet of head on these valves (* 20.8 psig). This head will preclude any leakage through this penetration. During the recirculation phase of safey injection, these valves are open to provide flow to ND pump suction.

23. The main steam, feedwater, auxiliary feedwater, sample and blowdown lines are all connected to the secondary side of the steam generator which is kept at a higher pressure than the primary side soon after a LOCA occurs.

Any leakage between the primary and secondary sides of the steam gene-rator is directed inward to the containment.

24. Deleted

25. Type C leak test not required by 10 CFR 50, Appendix J because these containment isolation valves:

a. Do not provide a direct connection between the inside and outside atmospheres of the primary reactor containment under normal opera-tion.

b. Are not required to close automatically upon receipt of a contain-ment isolation signal in response to controls intended to effect containment isolation, and

c. Are net required to operate intermittenly under post accident conditions.

In addition, these penetrations have been evaluated per 10CFR50, Appen-dix J, III.A.d. It was concluded that testing was not required.

l

26. These valves are sealed against leakage by the Containment Valve Injec-tion Water System as discussed in Section 6.2.4.4.

27. Type B test performed per 10 CFR 50, Appendix J.

28. Deleted

29. This system is required to be in operation during the Type A test in order to maintain the unit in a safe condition. Therefore, this penetra-tion will not be vented and drained.

l l 30. This penetration is a part of a closed system inside containment. All l piping inside containment is seismic Category 1 and therefore not subject to rupture as a result of a LOCA. This penetration will not be drained and vented for the Type A test.

Rev. 8

TABLE 6.2.4-1 (Page 13)

Containment Isolation Valve and Actuator Data

31. These penetrations are left open during an accident in order to provide reactor coolant pump seal water flow from the centrifugal charging pumps.

32. This penetration is effectively water sealed against any leakage directed out of containments by the residual heat removal pumps discharge pressure.

33. This penetration is effectively water sealed against any leakage directed out of containment by the centrifugal charging pumps discharge pressure.

34. An effective fluid seal on these penetrations, provided by the suction sources to the residual heat removal pumps during and following an accident.

35. This penetration is left open during an accident to provide flow from the centrifugal charging pumps to the reactor vessel.

36. An effective fluid seal on these penetrations prevents any leakage directed out of containment. Residual upper head injection accumulator pressure () Pa) would direct any leakage through this penetration into containment.

37. System presents a Seismic Category I closed pressure boundary to the containment atmosphere following a LOCA and is not a part of the reactor coolant system pressure boundary. In addition, the outside containment e isolation valve for each penetration is supplied by the Containment Valve Injection Water System as discussed in Section 6.2.4.4, which provides a sesl against any leakage through the valve.

38. These penetrations are in use during and following an accident to provide Containment Valve Injection Water System flow to certain containment isolation valves. In the event that the containment isolation valve on

. these penetrations should fail to open, an effective water seal would be maintained on the penetration at a pressure > Pa by the Containment Valve Injection Water Surge Chamber.

39. These penetrations will e!ther be in use following an accident, or will be sealed against leakage by a water seal against the outside of the penetrations. In addition, the following steps are taken to provide additional assurance of penetration integrity:

a. The outside containment isolation valves are supplied by the Containment Valve Injection Water Systems, as discussed in Section 6.2.4.4, which provides a seal against leakage.

b. The check valves which provide the inside isolation, are tested per Technical Specification 4.4.7.2.2, which requires a water leak test for Reactor Coolant System Pressure Isolation Valves.

Rev. 8

-m:- n~ -

TABLE 6.2.4-1 (Page 14)

Containment Isolation Valve and Actuator Data The use of the above features to assure the integrity of these penetrations avoids the necessity of installing block valves in the injection flow path. Such valves would add an increased probability of flow path blockage during an accident.

40. The leakage through these lines will be included in the results of the Type A test.

7 Rev. 8 i -

Table 6.2.4-2 (Page 2)

Comparison of Containment Purge System With Branch Technical Position CSB 6-4, Revision 2 Paragraph Compliance Status the probability of debris entrainment in the valves.

B-2 In Compliance. See description of Contain-ment Purge System in Section 9.4.5.

B-3 In Compliance. See description of Contain-ment Auxiliary Charcoal Filter System in Section 9.4.6.

B-4 In Compliance. See Sections 6.2.4 and 6.2.6.

B-5-a The loss-of-coolant accident analysis does

B-5-b not assume the purge valves are open at the onset of the postulated LOCA. Purge system operation is limited to < 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per year in accordance with SRP 6.2.4 guide-lines. Lower compartment purge valves are closed during power, startup, hot standby I and shutdown modes of operation (Modes 1-4).

B-5-c If the system is in operation at the start of an accident the amount of air lost while I the valves are closing is insignificant. (See response to Question 42.64, McGuire FSAR)

The minimum containment pressure analysis is presented in Section 6.2.1.5.

B-5-d An allowable leak rate for these valves will be developed in the Type "C" test program.

Rev. 8

~ -_

Table 6.2.4-2 (Page 1)

Comparison of Containment Purge System With Branch Technical Position CSB 6-4, Revision 2 Paragraph Compliance Status B-1-a The Containment Isolation System is des-cribed in Section 6.2.4. Operability of the containment purge isolation valves is currently under review by the Equipment Qualifications Branch. (Reference E. G.

Adensan's April 1, 1982 letter to W. O.

Parker.)

B-1-b The system has a total of nine supply and exhaust penetrations (as shown on Figure 9.4.5-1) in order to serve the upper and lower compartments of the ice condenser containment and to limit the penetration sizes.

B-1 c Containment penetration and isolation valve sizes are listed in Table 6.2.4-1.

Note that SRP 6.2.4 states that the 8 inch maximum duct diameter recommendation is not applicable since purge system opera-tion is Technical Specification limited to < 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per year during power, l startup, hot standby and shutdown modes of operation (Modes 1-4).

B-1-d In Compliance. See Section 6.2.4.

B-1-e In Compliance. See Section 6.2.4.

B-1-f In Compliance. See Section 6.2.4.

B-1 g The potential for entrainment of debris in the containment purge isolation valves is minimized by the ice condenser contain-ment design. Since the lower containment purge isolation valves will be closed during power, startup, hot standby and shutdown modes of operation (Technical Specification requirement), any debris generated from the postulated LOCA would be confined to the lower compartment by the ice condenser's filtering the debris. The upper contain-ment isolation valves are not in the ice condenser blowdown stream, further reducing Rev. 8

. - _ ~

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