Text

Site, Core Operating Limits Report (COLR)
	ML050910142
Person / Time
Site:	Oconee
Issue date:	03/21/2005
From:	Rosalyn Jones; Duke Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ONEI-0400-50, Rev 24
	Download: ML050910142 (18)
	v • d • e

9_ Duke RON A. JONES Vice President tiPowere Oconee Nuclear Site A Duke Energy Company Duke Power ONOI VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax March 21, 2005 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Site Docket No. 50-269 Core Operating Limits Report (COLR)

Gentlemen:

Attached, pursuant to Oconee Technical Specifications 5.6.5, is an information copy of a revision to the Core Operating Limits Report for Oconee Unit 1, Cycle 22, Rev. 24, Unit 2, Cycle 21, Rev. 2 nd Unit 3, Cycle 22, Rev. 22.

Ver r y yours, R. es site, Vice President Oconee Nuclear Site Attachment I

4ceI www. dukepower. corn

NRC Document Control Desk March 21, 2005 Page 2 xc w/att: Mr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site

DISPOSITON OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY SuperRush THE TRANSMITTAL StGNATURE UNLESS RECIPIENT IS Date: 03114105 OTHERWISE IDENTIFIED BELOW

1) 00620 DOC MGMT MICROFILM EC04T Document Transmittal #: DUK050730040

2) 00813 DOC MGMT EC04T ORIGINAL

3) 06358 ONS REGUL COMPLIANCE ON03RC Duke Power Company QA CONDITION

Yes F~No

4) 06700 ONS MANUAL MASTER FILE ON03DM DOCUMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED []Yes IF OA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE

5) 06937 R RST CLAIR ECO8G REFERENCE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO-NUCLEAR GENERAL OFFICE Duke Power Company OCONEE NUCLEAR STATION P.O. Box 1006 WORK ITEM: EXEMPTION M-5 Energy Center EC04T RECORD RETENTION: 003587 Charlotte, N.C RESP GROUP: NE CORE OPERATING LIMITS REPORTS Rec'd By ___ _

Page I of I Date I

DOCUMENT NO 1-QACOND REV #1DATEI

-I DISTR CODE 1 2 3 4 6 7 18 9 10 11 12 13 14 115 TOTAL ONEI-0400-050 1 024 03114/05 NOMD-27 x VI VII V1 4 ONEI-0400-051 1 023 03114105 ONEI-0400-070 1 022 03/14/05 SEE REMARKS FQR INFORMATJOrN ONLY REMARKS: DUKE . . . . . . . THOMAS . I . I . . . .

OCONEE ICYCLE 22 - OCONEE 2CYCLE 21 - OCONEElICYCLE 22 C GEER DOCUMENTS RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM. NUCLEAR STATION ENGR MANAGER FOR EACH DOCUMENT SEE PAGE 3 FOR FILING INSTRUCTIONS GS-SVP NUCLEAR SUPPORT BY:.-

J W SIMMONS JWSITER EC08H

ONEI-0400-50 Rev 24 Page 1 of 33 Duke Power Company Oconee 1 Cycle 22 Core Operating Limits Report QA Condition 1 Prepared By: L. D. McClain /;;IyMQuin/; T0 4 \g Date: lOflar 205 d

Checked By: J. M. Sanders 1< Date: /d1k .6'y-CDR By: S. G.Siry / 1, b. &A4 Date: l) 1 Mar 2 O°;5 N

Approved By: Date: / OI 4 a 2L)F

Document No. / Rev. ONEI-0400-50 Rev. 24 Date March 9,2005 Page No. Page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date: 3ao/vf (Sponsor)

CATAWBA Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) [ Inspected By/Date:

RES (Reactor) [ Inspected By/Date:

MOD [l Inspected By/Date:

Other ( ) [ Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( l) Inspected By/Date:

MCGUIRE Inspection Waived MCE (Mechanical & Civil) E Inspected By/Date:

RES (Electrical Only) E Inspected By/Date:

RES (Reactor) E Inspected By/Date:

MOD D Inspected By/Date:

Other ( _ ) El Inspected By/Date:

ONEI-0400-50 Rev 24 Page 3 of 33 Oconee 1 Cycle 22 Core Operating Limits Report Insertion Sheet for Revision 24 This revision is not valid until the end of operation for Oconee 1 Cycle 21.

Remove these revision 23 pages Insert these revision 24 pages 1 -5 1-5 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 1 Cycle 22 revisions below 24 Mar2005 1-5 - - 33 23 Feb 2005 1 - 4, 6 - - 33 22 Dec 2004 1 - 3,30 - - 33 21 Feb 2004 1 - 4, 6 - - 33 20 Nov 2003 1 - 32 33 - 33

,Oconee 1 Cycle 21 revisions below 19 Aug 2003 1,2,3 la - 32 18 Apr2002 1,2,4 - - 32 17 Mar2002 1-31 32 - 32 Oconee 1 Cycle 20 revisions below 16 May 2001 1-4 - - 31 15 Nov 2000 1-31 - - 31

ONEI-0400-50 Rev 24 Page 4 of 33 Oconee 1 Cycle 22 1.0 Error Adjusted Core Operating Umits The Core Operating Limits Report for 01 C22 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified in references 1 through 11. The RPS protective limits and maximum allowable setpoints are documented in references 12 through 14. These limits are validated for use in 01 C22 by references 15 through 17. The 01 C22 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (F~h) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10 F provided 4 RCPs are in operation and Tavg does not decrease below 569 "F.

The error adjusted core operating limits Included In section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 01 C22 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3/SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November 23,1992.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A, Revision 1, SER dated October 1, 1985.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001 A, Revision 5, SER dated December 8,2000.

4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A. Revision 1, SER dated June 23,2000.

5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8,1999.

6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, Revision 0, SER dated April 3,1995.

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003.

8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 3, SER dated September 24, 2003.

9. BAW-1 0192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.

10. BAW-10164P-A, Rev. 4, 'RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis', SER dated April 9, 2002.

11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, SER dated February 4, 2000.

12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit, OSC-4048, Revision 4, January 2001.

13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.

14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.

15. 01C22 Maneuvering Analysis, OSC-8413, Revision 6, March 2005.

16. 01 C22 Specific DNB Analysis, OSC-8460, Revision 1, September 2003.

17. 01C22 Reload Safety Evaluation, OSC-8471, Revision 3, February 2005.

ONEI-0400-50 Rev 24 Page 5 of 33 Oconee 1 Cycle 22 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.

Referred to by TS 3.5.4.

Spent fuel pool boron concentration shall be greater than 2220 ppm.

Referred to by TS 3.7.12.

The equivalent of at least 1100 cubic feet of 11,000 ppm boron shall be maintained in the CBAST.

Referred to by TS SLC 16.5.13.

CFT boron concentration shall be greater than 1835 ppm. The average boron concentration in the CFT's shall be less than 4000 ppm. Referred to by TS 3.5.1.

RCS and Refueling canal boron concentration shall be greater than 2220 ppm.

Referred to by TS 3.9.1.

Shutdown Margin (SDM) shall be greater than 1% Ak/k.

Referred to by TS 3.1.1.

Moderator Temperattire Coefficient (MTC) shall be less than: MTC x 10-4 Unear interpolation is valid within the table provided. Ap/°F % FP Referred to by TS 3.1.3. +0.70 0

+0.57 15 0.00 80 0.00 100 0.00 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by TS 3.4.1. 4 RCP: measured hot leg pressure > 2125 psig 3 RCP: measured hot leg pressure > 2125 psig DNB parameter for RCS loop average temperature shall be: Max Loop Tavg (Incl 20F unc)

Referred to by TS 3.4.1. ATc, 0 F 4 RCP Op 3 RCP Op 0 581.0 581.0

The measured Tavg must be less than COLR limits minus 1 581.4 581.2 Instrument uncertainty. ATc Is the setpoint value selected by 2 581.8 581.4 the operators. Values are expanded by linear interpolation on 3 582.1 581.7 page 33 of this document without instrument uncertainty. 4 582.5 581.9 5 582.9 582.1

This limit is applied to the loop with the lowest loop average temperature consistent with the NOTE in SR 3.4.1.2. All other temperature limits apply to the maximum loop Tavg.

DNB parameter for RCS loop total flow shall be: 4 RCP: Measured > 108.5 %df Referred to by TS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.

Referred to by TS 3.2.1.

Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.

Referred to by TS 3.2.1.

Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overlap requirements are met as these situations are explicitly addressed by TS 3.1.4 (Control Rod Group Alignment Umits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3 (Quadrant Power Tilt).

ONEI-0400-51 Rev 23 Page 1 of 33 Duke Power Company Oconee 2 Cycle 21 Core Operating Limits Report QA Condition 1 Prepared By: L. D. McClain/V G Miu Date: 10) Ylar2a95 1, , .-

Checked By: J. M. Sandei Date: OO V ZO°)

CDR By: R. A. Hight / R,(A I 1 -I -

t(ak Date: IC) MYa C,;

Approved By:. Date: /: o /-1,cADDS

Document No. /Rev. ONEI-0400-5 IRev. 23 Date March 9. 2005 Page No. Pace 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:

I Date: 2Lf°L° (Sponso)

CATAWBA Inspection Waived MCE (Mechanical & Civil) a Inspected By/Date:

RES (Electrical Only) D Inspected By/Date:

RES (Reactor) n Inspected By/Date:

MOD a Inspected By/Date:

Other ( l) Inspected By/Date:

OCONEE Inspection Waived

.) MCE (Mechanical & Civil)

RES (Electrical Only)

[r Inspected By/Date:

Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD Inspected By/Date:

Other ( ) [ Inspected By/Date:

MCGUTRE Inspection Waived MCE (Mechanical & Civil) 13 Inspected By/Date:

RES (Electrical Only) 0 Inspected By/Date:

RES (Reactor) 5 Inspected By/Date:

MOD a Inspected By/Date:

Other ( ) D Inspected By/Date:

ONEI-0400-51 Rev 23 Page 3 of 33 Oconee 2 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 23 This revision is not valid until the end of operation for Oconee 2 Cycle 20.

Remove these Revision 22 pages Insert these Revision 23 pages 1 -5 1 -5 Revision Log Effective Pages Pages Pages Total Effective IOconee Revision l 23 22 Date Mar 2005 Dec 2004 Revised 2 Cycle 21 revisions below 1- 5 1 - 3,30 Added Deleted

-33 Pages 33 21 Apr2004 1 - 33 33 lOconee 2 Cycle 20 revisions below 20 Feb 2004 1 - 3,5 ;- - 33 19 Nov 2003 1-4,8-10.12-13,29 la - 33 18 Oct 2002. 1-3,14,16,24,30 - - 32 17 Oct2002 1 - 31 32 - 32 1Oconee 2 Cycle 19 revisions below 16 May 2001 1 31 Oconee 2 Cycle 18 revisions below 15 Apr2001 1-4 - - 31 14 Feb2000 1-4 - - 31 13 Nov`1999 1 - 31 - - 31 12 Sep'1999 1 - 31 - - 31 11 Apr1999 1 - 4, 6 - - 31 10 Mar'1999 1 - 31 - - 31

ONEI-0400-51 Rev 23 Page 4 of 33 Oconee 2 Cycle 21 1.0 Error Adjusted Core Operating Limits The Core Operating Umits Report for 02C21 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified in references I through 11. The RPS protective limits and maximum allowable setpoints are documented in references 12 through 14. These limits are validated for use in 02C21 by references 15 through 17. The 02C21 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10oF provided 4 RCPs are in operation and Tavg does not decrease below 5690 F.

The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C21 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 / SIMULATE-3P, DPC-NE-1 004P-A, Revision 0, SER dated November 23, 1992.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A, Revision 1, SER dated October 1, 1985.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 5, SER dated December 8, 2000.

4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, Revision 1, SER dated June 23, 2000.

5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8, 1999.

6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, Revision 0, SER dated April 3, 1995.

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003.

8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 3, SER dated September 24, 2003.

9. BAW-1 01 92-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.

10. BAW-1 01 64P-A, Rev. 4, *RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SER dated April 9, 2002.

11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, SER dated February 4, 2000.

12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Umit, OSC-4048, Revision 4, January 2001.

13. Power Imbalance Safety Umits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.

14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.

15. 02C21 Maneuvering Analysis, OSC-8526, Revision 3, March 2005.

16. 02C21 Specific DNB Analysis, OSC-8561, Revision 0, November 2003.

17. 02C21 Reload Safety Evaluation, OSC-8609, Revision 0, April 2004.

ONEI-0400-51 Rev 23 Page 5 of 33 Oconee 2 Cycle 21 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.

Referred to by TS 3.5.4.

Spent fuel pool boron concentration shall be greater than 2220 ppm.

Referred to by TS 3.7.12.

The equivalent of at least 1100 cubic feet of 11,000 ppm boron shall be maintained in the CBAST.

Referred to byTS SLC 16.5.13.

CFT boron concentration shall be greater than 1835 ppm. The average boron concentration in the CFT's shall be less than 4000 ppm. Referred to by TS 3.5.1.

RCS and Refueling canal boron concentration shall be greater than 2220 ppm.

Referred to by TS 3.9.1.

Shutdown Margin (SDM) shall be greater than 1% AkIk.

Referred to by TS 3.1.1.

Moderator Temperature Coefficient (MTC) shall be less than: MTC x 10-4 iUnear interpolation is valid within the table provided. Ap/ 0 F % FP

- - Referred to by TS 3.1.3. +0.70 0

+0.57 15 0.00 80 0.00 100 0.00 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by TS 3.4.1. 4 RCP: measured hot leg pressure > 2125 psig 3 RCP: measured hot leg pressure > 2125 psig DNB parameter for RCS loop average temperature shall be: Max Loop Tavg (Incl 20 F unc)

Referred to by TS 3.4.1. ATc, 'F 4 RCP Op 3 RCP Op 0 581.0 581.0

The measured Tavg must be less than COLR limits minus 1 581.4 581.2 instrument uncertainty. ATc is the setpoint value selected by 2 581.8 581.4 the operators. Values are expanded by linear interpolation on 3 582.1 581.7 page 33 of this document without instrument uncertainty. 4 582.5 581.9 5 582.9 582.1

This limit is applied to the loop with the lowest loop average temperature consistent with the NOTE in SR 3.4.1.2. All other temperature limits apply to the maximum loop Tavg.

DNB parameter for RCS loop total flow shall be: 4 RCP: Measured > 107.5 %df Referred to byTS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.

Referred to by TS 3.2.1.

Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.

Referred to by TS 3.2.1.

Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overlap requirements are met as these situations are explicitly addressed by TS 3.1.4 (Control Rod Group Alignment Limits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3 (Quadrant Power Tilt).

ONEI-0400-70 Rev 22 Page 1 of 33 Duke Power Company Oconee 3 Cycle 22 Core Operating Limits Report QA Condition 1 Prepared By: JL.D.Mc.lainders/ = Date: lOlflar f D9S5 Checked By: J. M. Sanders g I -

Date: 44f/7ber T-I CDR By: G.J. Byers )A\ a Date: 4xo IfrA Approved By:. Approved By: Date :

Date: 9 C /

Document No. / Rev. ONEI-0400-70 Rev. 22 Date March 10. 2005 Page No. Pate 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: ig -r/ Date: 3 /4O/f (Sponsor)

CATAWBA Inspection Waived MCE (Mechanical & Civil) S Inspected By/Date:

RES (Electrical Only) a Inspected By/Date:

RES (Reactor) 5 Inspected By/Date:

MOD D Inspected By/Date:

Other ( ) ] Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) IA Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) Inspected By/Date:

MOD [( Inspected By/Date:

Other ( l) Inspected By/Date:

MCGUIRE Inspection Waived MCE (Mechanical & Civil) a Inspected By/Date:

RES (Electrical Only) D Inspected By/Date:

RES (Reactor) 5 Inspected By/Date:

MOD [l Inspected By/Date:

Other ( ) a Inspected By/Date:

ONEI-0400-70 Rev 22 Page 3 of 33 Oconee 3 Cycle 22 Core Operating Limits Report Insertion Sheet for Revision 22 i This revision is not valid until the end of operation for Oconee 3 Cycle 21. l Remove these Revision 21 pages Insert these Revision 22 pages 1-5 1-5 Revision Log Effective Pages Pages Pages Total Effective

. Revision Date Revised Added Deleted Pages lOconee 3 Cycle 22 revisions below 22 Mar2045 1-35 - - 33 21 Nov 2004 1 - 33 - - 33

[Oconee 3 Cycle 21 revisions below 20 Sep 2004 1 - 4, 6 - - 33 19 Feb 2004 1 - 4, 6 - - 33 18 Nov.2003 1 - 3,5 - - 33 17 Apr. 2003 1 - 31 32-33 - 33 rOconee 3 Cycle 20 revisions below 16 Oct.2002 1 - 3, 5 - - 31 15 Nov. 2001 1-3 - - 31 14 Nov.2001 1 -31 - - 31

ONEI-0400-70 Rev 22 Page 4 of 33 Oconee 3 Cycle 22 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 03C22 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified In references 1 through 11. The RPS protective limits and maximum allowable setpoints are documented in references 12 through 14. These limits are validated for use in 03C22 by references 15 through 17. The 03C22 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10F provided 4 RCPs are In operation and Tavg does not decrease below 569 0F.

The error adjusted core operating limits included in section 1 of the report Incorporate all necessary uncertainties and margins required for operation of the 03C22 reload core.

1.1 References

1. Nuclear Design Methodology Using CASMO-3 ! SIMULATE-3P, DPC-NE-1 004P-A, Revision 0, SER dated November 23, 1992.