IR 05000237/1987039
| ML17199T482 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/23/1987 |
| From: | Gardner R, Westberg R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| 50-237-87-39, 50-249-87-38, GL-85-06, GL-85-6, NUDOCS 8712310007 | |
| Download: ML17199T482 (5) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION REGION I I I Report Nb. S0-237/87039(DRS); 50-249/87038(DRS)
Docket No. 50-237 Docket No. 50-249 License No. DPR-19 License No. DPR-25 Licensee:
Commonwealth Edison Company P. 0. Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Units 2 and 3 Inspection At:
Dresden Site, Morris, Illinois Inspection Conducted:
November 30 through December
~ft-VJ~
Inspector:
RolfA~tberg
~
J~
Q. Qc.L-Gvr~{~ [ Approved By:
~~ald N. garMer, Chief
Plant Systems Section*
Inspection Summary 11, 1987
\\'°),./ ).3 / 8'1 Date Inspection during the period of November 30 through December 11, 1987 (Report
. No. 50-237/87039(DRS); No. 50-249/87038(DRS)).
.
.
Areas Inspected:
Routine, announced inspection of the licensee's implementation of Generic Letter 85-06 relative to ATWS Mitigating Systems (25020).
Results:
Temporary Instruction (TI) 2500/20 was close No violations or deviations were identified.
B71'.t310007 871223
~ *
PDR ADOCK 05000237 Q
- . ~*-r.:;:~...*.
'*.
DETAILS
1~
Persons Contacted Commonwealth Edison Company
- C. Schroeder, Services Superintendent J. Brunner, Assistant Superintendent - Technical Services E. Armstrong, Regulatory Assurance Supervisor M. Korchynsky, Assistant Technical Staff Supervisor Menozi~ Nuclear Shift Operator
- R. Dyer, Technical Staff Engineer
- R. Stols, Quality Assurance Engineer
- J. Williams, Regulatory Assurance Engineer Other personnel were contacted during the course of the* inspectio *Indicates those attending th~ exit.on December 11, 198 TI 2500/20 ~ Compliance With ATWS Rule, 10 CFR 50.62 The purpose of this inspection was to determine* that ATWS mitigating.
- sys terns that a re not safety re 1 a ted comply with the 10 C FR 50. 62 rule,
. to determine whether the QA controls applied to the design, procurement,*
installation, and testing for ATWS equipment comply with Generic Letter No. 85--06, 11QA Guidance For ATWS Equipment That is Not Safety Related,
and *to assess the operational readiness of the ATWS equipment that is not safety relate *
The modifications to install the Recirculation Pump Trip (RPT) and the Alternate Rod Injection (ARI) systems, No. M12-2/3-79-23 and No. M12-2/3-81-04, were completed in 1981 and 1984 respectivel The modification to the Standby Liquid Control System (SLCS) to install a second suction line to allow simultaneous operation of two pumps on modification No. M12-2-84-119 was completed in 198 The ATWS modifications were not required to be classified as safety related; however, the licensee classified the RPT, ARI and SLCS as safety related due to their interface with existing safety related equipment. Therefore, design, procurement, installation, testing, and training was performed in accordance with the existing CECo Appendix B Quality Assurance Program, which exceeds the guidance given in Generic Letter 85~0 *
Since the RPT, SRI, and SLCS modifications are essentially complete and they were accomplished in accordance with an Appendix B QA program, this inspection concentrated on the confirmation of completed work and reviewed the design, procurement, and installation based on completed modification packages and a selective walkdown of ATWS systems.
- . ~'S::"'..-_......* -
"
)
- Documents Reviewed (1)
Modification Packages ta)
M12-2-79-23 (b)
M12-3-79-23 (c)
M12-2-81-04
- (2)
Schedule for complying with ATWS rule, dated October 18, 198 (3)
Safety Evaluation in support of.the BWR Owners Group's licensing topical response to. the ATWS rule, dated October 21, 198 (4)
Generic Letter 85-06, "Quality Assurance Guidance for ATWS Equipment That is Not Safety Related.
(5)
Surveillance Procedures (a)
(b)
DIS 260-3 11ATWS RPT/ARI Master Trip Unit Calibration Check", Revision DIS 260-4, 11ATWS Transmitter Calibration and Logic Tests", Revision (6)
Emergency Operating Procedures ( 7)
(a)
DEOP 100, i*Reactor Control, 11 Revision (b)
DEOP 100-1, "Reactor Level Control, 11 Revision (c)
DEOP 100-3, "Reactor Power Control, 11 Revision (d)
DEOP 400-4, "Level/Power.Controls, 11 Revision (e)
DEOP 500-1, "Alternate Standby Liquid Control Injection,
Revision Purchase Orders (a)
No. 501482 - Pu sh Butto (b)
No. 236784 - Control Panels and Power Suppl (c)
No. 236785 - ATWS RPT Cabine (8)
Receipt Inspections (a)
PO No. 501482 dated 10/24/8 (b)
PO No. 236784 dated 2/4/8 (c)
PO No. 236785 dated 10/19/8 (9)
Functional Test for Modification No. M12-2-79-2 (10) Operational Test for Modification No. M12-2-79-2 (11) Schematic Diagrams (a)
12E6582A - 12E6582 (b) * 12E242 (c)
12E242 (d)
12E2575 Inspect1on R~sult~
(1) Design Engineering The inspector reviewed the.licensee's responses to 10 CFR 50.62,
"The ATWS Rule; "Generic Letter 85-06; and Design Change Packages M12-2-79-23, M12-3-79-23, and M12-2~81-04. This review of selected portions of the licensee's design, indicated that it was properly implemented and did not compromise the safety features of the existing Reactor Protection Syste (2) Procurement and Installation At' the time of this inspection, the ATWS mitigating systems were installed with the exception of the Unit 3 Standby Liquid Control System modification, which is scheduled to begin duririg the Spring 1988 Outag Therefore, no inprocess inspection of the installation of ATWS systems was possibl The inspection verified the following aspects of the completed installations through a review of the modification packages and a selective sys tern wa 1 kdown. *
(a)
Procurement packages for the ATWS control panels, the DC power supplies and the actuation switches were reviewed and found consistent with the technical requirements of the ATWS desig (b)
Receipt inspections for the above equipment were accomplished in accordance with the CECo QA progra (c)
W~lkdown of a portion of th~ ARI/RPT system indicated that the instrumentation and control equipment was installed in the proper locatio * (d)
The ARI/RPT was physically and electrically independent of the existing safety related system (3) Confirmation of Completed Work Review of the ARI/RPT system verified the following:
(a)
(b)
(c)
(d)
- . ( e)
(f)
Operating procedures for initiation of ATWS mitigating systems, DEOP 100, DEOP 100-3, DEOP 400-7, and DEOP 500-1, were in place and the operators trained in their us Surveillance procedures DIS 260-3 and DIS 260-4 were in place and properly implemente Review of the Functional Test and Operational Test for the RPT system indicated that the logic was tested at pow~r following the installatio Walkdown of the system verified the installation the system bypass switches for testing and indication of system bypass on panels No. 2203-70A and N ~70 Review of the ATWS schematic control diagrams indicated that once the system was initiated, the ARI. system would complete it's action and return to normal operation would require additionil deliberate ~ctio~ Manual initiation capability of the ATWS mitigation system was verified in the Control Roo~.
(4) Quality Assurance and Qualifications The* ATWS mitigation system was designed,* installed, and.tested under the CECo 10 CFR 50, Appendix B, QA progra Personnel contacted or interviewed during this inspection appeared knowledgeable and capable of implementing the syste.
Exit Interview The inspector met with licensee representatives denoted in paragraph 1 during and at the conclusion of the inspection on December 11, 198 The ins~ec~ion summarized the scope and results of the inspection and discussed the likely content of this inspection report. *The licensee acknowledged the information and did not indicate that any of the information disclosed during the inspection could be considered proprietary in natur