ML20248A098
| ML20248A098 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/01/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 C311-89-2082, GL-89-06, GL-89-6, NUDOCS 8908080198 | |
| Download: ML20248A098 (2) | |
Text
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GPU Nuclear Corporation NUCIMF-Post Office Box 480 Route 441 South Middletown, Pennsylvar.la 17057 0191 717 044 7621 TELEX 84 2386 Writer's Direct Dial Number:
August 1, 1989 r
C311-89-2082 U. S. Nuclear Regulatory Commission Attn: ' Document Control Desk Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Response to Generic Letter 89-06, Safety Parameter Display System
.In accordance with NRC Generic Letter 89-06, Safety Parameter Display System, dated April 12, 1989, GPUN hereby certifies that the TMI-1 Safety Parameter Display System (SPDS) has been implemented and meets the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342, with the clarifications outlined in the attachment.
Supporting documentation, including the Generic Letter checklist and SPDS photographs, used to establish TMI-1 SPDS implementation status are available onsite.
The pre-implementation and design review of the TMI-1 SPDS was completed as described in NRC supplemental safety evaluation dated February 26, 1988. The TMI-1 SPDS was made operational prior to the start of Cycle 6 operation in March 1987.
Sincerely, H. D. F kill l
Vice President and Director, TMI-1 HDH/DJD/1ml Attachment
.cc: R. Hernan Sworn and subscribed to I
W. Russell before me this /5f day of I
J. Stolz
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l ATTACHMENT Clarification of Compliance to NUREG-0737, Supplement 1 and NUREG-1342 i-The TMI-1 SPDS meets the intent of NUREG-1342 with the following clarifications:
1.
NUREG-1342,Section III.A.3:
The TMI-1 Plant Computer currently uses out-of-range checks and substitution with good / valid inputs where redundant sensors are available. GpVN committed to evaluate the addition of advanced data validation schemes once the new comauter had been installed and the methods had been further evaluated (GPUN letter 5211-86-2064, dated April 25, 1986).
Installation of the new plant computer will be completed during'the BR outage. The redundant sensor algorithm software for appropriate parameters has been written for the new computer.
Evaluation will begin subsequent to incorporation of this software on the computer.
2.
NUREG-1342,Section III.A.3:
The Validation and Verification program identified that during an extreme condition when all of the computer programs are activated on the existing computer system, the SPDS response time may be impacted.
The SPDS programs are placed as high in priority as possible on the existing computer system. The timing requirements as they presently exist are adequate based on our experience. Since the new plant computer has increased processing power, this concern will be eliminated when the new plant computer is fully operational following the 8R outage.
3.
NUREG-1342,Section III.F.1:
l NRC SER dated February 26, 1988 indicates all issues and confirmatory items were adequately addressed; however, the GPUN basis for exclusion of DHR flow from the list of SPDS parameters specific to TMI-1 has not been addressed in the SER. Detailed justification for this exclusion was submitted to the NRC (GPUN letter 5211-86-2064, dated April 25, 1986), and our basis for exclusion of indication of DHR flow remains valid.
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