ML20246L321
| ML20246L321 | |
| Person / Time | |
|---|---|
| Site: | Seabrook |
| Issue date: | 07/12/1989 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM GL-89-06, GL-89-6, NYN-89087, NUDOCS 8907180396 | |
| Download: ML20246L321 (4) | |
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Ted C. Feigenbaum U
Vice President NYN 89087 l
July 1~2, 1989 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk References a) Facility' Operating License No NPF-67, Docket No. 50-443 b) USNRC Generic Letter 89-06 dated April 12, 1989 " Task Action Plan Item I.D.2 - Safety Parameter Display System"
Subject:
Response to Generic Letter 89-06 Gentlemen:
Generic Letter 89-06 requested information pursuant to 10 CFR 50.54(f) regarding the implementation of Safety Parameter Display System (SPDS) requirements. New Hampshire Yankee (NHY) Fas reviewed the design, operation and related aspects of the Seabrook Station SPDS against the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342. New Hampshire Ycnkee certifies that the Seabrook Station SPDS meets the requirements of NUREG-0737, Supplement 1, taking into account the information provided in NUREG-1342 with the exceptions noted in Enclosure 1.
In addition to the noted exceptions, Enclosure 1 describes two minor concerns effecting the reliability of the SPDS discovered as a result of normal operation. It also describes the potential for improvement of instrumentation calibration procedures. Action will be taken to correct the exceptions, and correct or review the additional items as described in in order that the Seabrook Station SPDS will fully meet the abovo requirements.
Documentation upon which the above certification is based including the completed checklist and photographs shall be maintained for at least three years.
If you have any questions regarding this matter, please contact
.Mr. Geoffrey Kingston at (603) 474-9521, extension 3371.
Very truly yours, 8907180396 890712
/
PDR ADDCK 05000443 C# ~ N P
PNV Ted C. Feigenbaum Enclosure 00AI New Hampshire Yonkee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474-9521
~~ United States Nuclear' Regulatory Commission July 12, 1989 Attentions' Document Control Desk-Page 2.
cc:
Mr. William T. Russell Regional Administrator l
United States Nuclear Regulatory Commission j.l Region I 475 Allendale Road l-King of Prussia,-PA-19405 Mr. Victor Nerses, Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington.DC 20555 NRC Senior Resident Inspector P.O. Box 1149 Seabrook Station, NH 03874 STATE OF NEW HAMPSHIRE Rockingham, ss.
July 12, 1989 Then personally appeared before me, the above-named Ted C. Feigenbaim who, being duly sworn, did state that he is Vice President Engineering, Licensing and Quality Programs of New Hampshire Yankee, that he is duly authorized to execute and file the foregoing information in the name and on the behalf of New Hampshire Yankee, and that the statements therein are true to the.best of his knowledge'and belief.
Mary E. Sloan, Notary Public My Commission Expires: January 8, 1992 1
Y V
ENCLOSURE 1 TO NYN-89087 Exceptions to SPDS Implementation Requirements at Seabrook Station EXCEPTION la SPDS Availability Data New Hampshire Yankee has committed to collect SPDS availability data during the first operating cycle and report this data to the NRC prior to startup following.the first refueling outage. The purpose of this data collection is to detenmine SPDS reliability under operating plant conditions. This data collection cannot be completed until Seabrook Station Unit I completes its first cycle of operation. Preliminary data is being collected and results for the first half of 1989 indicate SPDS availability greater than 99.4 percent.
EXCEPTION 2:
SPDS Response Time The response time of the SPDS under heavily loaded conditions has not been evaluated. Heavily loaded conditions are conditions of high demand imposed upon the main plant computer system (HPCS) such as during a plant transient which initiates many alarms and results in increased operator information demand. A test will be performed to evaluate the response time of the SPDS under heavily loaded conditions; and the test results will be reported to the NRC prior to startup following the first refueling outage.
EXCEPTION 3: RDMS Fuse-Dependent Isolation Devices The Seabrook Radiation Data Management System (RDMS) employs isolation devices which depend upon a fuse in order to perform the electrical isolation function. These fuse-C9 pendent isolation devices have been accepted by the NRC for interim use and are expected to be replaced with non-fuse-dependent isolation devices by September 30, 1989.
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- Uinor Concerns Effecting the Reliability of the SPDS at Seabrook Station Steam Generator Wide Range Level Density Compensation A recent design modification provided density compensation for steam generator wide range control room level indication. The design modification did not make the density compensated level measurement available to the MCPS inputs. The density compensated level measurement will be provided to the MPCS inputs by means of a software change by August 31, 1989.
RVLIS Full Range Level Reliability Interpretation Reactor Vessel Level Indicating System (RVLIS) full range level is the indicated reactor vessel level under conditions during which reactor coolant pumps (RCP's) are not operating. Whenever RCP's are operating, RVLIS full range level is driven to an off-scale high value. Because this is an expected condition, the SPDS is designed to recognize the off-scale high level as a reliable indication. However, it has been discovered that the implementation of this design feature resulted in the SPDS continuing to identify this off scale high level as an unreliable indication.
The above-described condition has been identified as an SPDS software problem and is expected to be corrected by August 31, 1989.
Potential for the Improvement of Instrumentation Calibration Procedures The SPDS review identified the potential for improvement of the programmatic requirements for instrumentation loop calibration where MPCS inputs are involved. Current instrument calibration procedures ensure that a calibrated measurement is available to the MPCS input portion of applicable process control and protection systems. However, calibration procedures do not specifically require follow-up action in the event that the MPCS output values of a given parameter do not agree with the expected value. In practice to date, suspect MPCS output indications observed during instrument calibration or normal operation have been subject to follow-up action. Furthermore, data validity checks built into the SPDS software remove inputs that are unreliable and, where applicable, remove inputs that fail an engineering range check or bandwidth check.
Observation of MPCS input performance over time has demonstrated a high I
degree of accuracy and reliability. Although this does not represent a deficiency in the performance of the SPDS, a more formal program will be evaluated and, if deemed appropriate, corrective action shall be completed by December 31, 1989.
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