ML20056C461
| ML20056C461 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/11/1993 |
| From: | Hutchinson C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-1342, RTR-NUREG-737, TASK-1.D.2, TASK-TM GL-89-06, GL-89-6, GNRO-93-00064, GNRO-93-64, NUDOCS 9306240169 | |
| Download: ML20056C461 (4) | |
Text
'N Entergy Operations,Inc.
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- June 11, 1993 gj[%,, y s.;,y, U.S. Nuclear Regulatory Commission Mail Station P1-37 Washington, D.C.
20555 Attention:
Document Control Desk
Subject:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Extension of Safety Parameter Display System (SPDS) Modification Schedule GNRO-93/00064 i
Gentlemen On July 11, 1989, Entergy Operations, Inc. (formally System Energy Resources, Inc.) submitted a response to Generic Letter (GL) 89-06, " Task Action Plan Item I.D 2 - Safety Parameter Display System (SPDS) ", regarding implementation of the Grand Gulf Nuclear Station (GGNS) SPDS.
GGNS was requested to provide certification that the SPDS fully meets, or would be modified to meet, the requirements of NUREG-0737, Supplement 1,
taking into account guidance provided in NUREG-1342.
Certification was provided along with a planned schedule for implementing long-term improvement modifications.- These modifications were scheduled to be completed by September 1, 1993 (Reference AECM-89/0109, dated 7/11/89).
Based on our certification and following the NRC SPDS audit in March 1987, the Staff concluded that GGNS would satisfactorily meet the requirements specified in NUREG-0737, Supplement 1-for an SPDS, provided the long-term improvements described in the aforementioned reference were completed on schedule (References MAEC-90/0120, dated.May 10, 1990).
The Staff also requested that they be notified upon full implementation or if the proposed date of full implementation of the SPDS,
-i.e.,
September 1, 1993, changed.
Entergy Operations, Inc., has completed the modifications
' identified in our July 11, 1989 submittal, except for those items requiring resolution of the SPDS verification and validation (V&V) discrepancies previously identified.
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I June 11, 1993 GNRO-93/00064 Page 2 of 5 modifications, which would be relatively costly and a drain on limited personnel resources if pursued separately, will be incorporated into the Plant Data System Project (PDS) which is projected to be completed by September 1, 1995.
The PDS will centralize operation of existing plant computers including SPDS and resolve the SPDS verification and validation discrepancies.
In addition, the PDS will incorporate an improved software quality program that will also enhance current V&V techniques.
In addition to efficient implementation of the PDS project, this schedule change is necessary in order to continue support of the Security System Upgrade. Project underway to improve intrusion alarm capabilities at GGNS.
This project is a major venture in terms of overall plant resources and utilizes some of the arme personnel needed for the SPDS work.
Members from the GGNS plant staff met with Region II security personnel on April 6, 1993 in Atlanta, Georgia to discuss the security upgrade project and its current status.
This upgrade is scheduled to be completed by the end of 1993.
As noted in our previous submittal (AECM-89/0109, dated July 11, 1989) the outstanding V&V discrepancies present no major limitations on the operation of the SPDS and, in retrospect, do not constitute essential elements for compliance with NUREG-0737, Supplement 1.
GGNS has also revisited its original position relative to Emergency Operating Procedures (EOPs) upgrades.
On April 1, 1988, GGNS submitted, pursuant to License Condition i
2.C. (3 6), Revision 1 to the Safety Analysis Report for SPDS which provides supporting evidence that the SPDS is designed to meet the requirements of Supplement 1 to NUREG-0737.
Section 2.1 of this report states, in part, " Industry experience in developing various SPDS designs has shown that SPDS displays are more meaningful and useful to operators during emergency situations when they are directly integrated with Emergency Procedures (EPs). "
In an effort to further enhance operator response capability, GGNS's commitments-exceeded NUREG-0737's intent of " integrating SPDS with emergency procedures" by developing and bzplementing EP j
support displays.
These displays are used to provide supporting data on specific emergency conditions during performance of the emergency procedures steps.
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June 11, 1993 GNRO-93/00064 Page 3 of 5 In October 1989, GGNS performed a safety evaluation (in accordance with 10 CFR 50.59) to temporarily remove the EP support displays function due to EOP changes that had not been incorporated into SPDS as a result of revisions to generic guidelines.
SPDS operators were instructed, and subsequently.
trained to use the overview display.
The information currently displayed on the SPDS overview display has proven sufficient to alert the operator of plant safety status in accordance with NUREG-0737, Supplement 1.
The overview display function provides the critical safety function parsmeters for each of the su2ety functions, i.e.,
reactivity control, reactor core cooling and heat removal from the primary system, reactor coolant system integrity, radioactivity control, and containment conditions, listed in the nupplement.
Furthermore, use of the overview function during normal operations, and during training exercises, has been determined less cumbersome for SPDS operators than the EP support displays.
Therefore, GGNS has elected to not implement planned modifications relative to amergency operating procedures (EOPs) support displays.
The existing SPDS overview display complies with NUREG-0737, Supplement i requirements, and the guidance of NUREG-1342, and will be used exclusiv L v to assist operators in determining the safety status
'e plant.
The GGNS SPDS Safety Analysis Report (SAR) w.
1,4 revised, via the 10CFR50.59 process, to reflect permanent Aeaoval of EP support displays.
If you have any questions or require additional information concerning this matter, please contact Ms. Jewel Summers at (601) 437-2149.
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Yours truly,
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a June 11, 1993 GNRO-93/00064 Page 4 of 5 cci Mr. R. H. Bernhard (w/o)
Mr. H. W. Keiser (w/o)
Mr.
R.-B. McGehee (w/o)
Mr. N. S. Reynolds (w/o)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/o)
Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St.,
N.W., Suite 290D Atlanta, Georgia 30323 Mr.
P. W.
O'Connor, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C.
20555 G9305201 - 4