ML20206H427
| ML20206H427 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/09/1987 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NYN-87049, NUDOCS 8704150352 | |
| Download: ML20206H427 (4) | |
Text
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PENHI Put2c SeMoe W h HampeNie NYN-87049 April 9, 1987 N:;w Hampshire Yankee Division United States Nuclear Regulatory Commission Washington, DC 20555 4
i Attention: Document Control Desk i
References:
(a) Facility Operating License NPF-56, Construciton Permit CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (NYN-87026), dated March 6,1987, " Safety i
Parameter Display System (SPDS); Completed Activities"
Subject:
Request for Additional Information; Safety Parameter Display System and Environmental Qualification j
Gentlemen:
During a recent discussion with the NRC Staff, New Hampshire Yankee (NHY) was requested to provide additional information concerning the implementation of certain SPDS design enhancements. This additional in-formation is provided in Attachment 1.
As also indicated in this attachment certain activities referred to in the Order of the ASLB's Initial Decision (ASLBP No. 82-47102-02) have been completed. Accordingly NHY requests that the resolution of these activities be reflected in the next supplement to Seabrook Station's SER.
i If the NRC should have any further questions regarding this matter do not hesitate to contact the NHY Bethesda Licensing Office (Mr. R. E.
l Sweeney) at (301) 656-6100.
Very truly yours, l
fh Al J
T. C. Feigenbaum 8704150352 870409 PDR ADOCK 05000443
, g6 P
_2 P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574
. ~ _ _
k United States Nuclear Regulatory Commission April 9, 1987 Attention: Document Control Desk Page 2 i
At tachment cc:
Mr. Victor Nerses, Acting Director PWR Project Directorate No. 5 Division of PWR Licensing A U. S. Nuclear Regulatory Commission
' Washington, DC 20555 Regional Administrat'or U. S. Nuclear Regulatory Commission.- Region I 631 Park Avenue King of Prussia, PA 19406 s
Mr. A. C. Cerne NRC Senior Resident' Inspector Seabrook Station Seabrook, NH 03874 Atomic Safety and Licensing Board Service List t
f
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ATTACHMENT'l TO NYN-87049 i-SAFETY PARAMETER DISPLAY SYSTEM RAIs
.1.
Addition of Maintenance Procedure to EQ File 1
The ASLB in its Partial Initial Decision indicated that a.
maintenance procedure should be developed and inserted into the appropriate environmental qualification file (EQ File) for the containment water. level transmitters prior to issuance of a 5% power license. The stated purpose was to ensure an ade-quate level of oil.is continuously present in the silicone-filled riser-assemblies associated with these transmitters.
NHY has. completed this activity and the EQ File is ready l
for NRC inspection.
i 2.
Continuous Display of Top Level Critical Safety Function (CSF)
Summary In Reference (b), NHY indicated that the top-level CSF summary had been added to all CRT formats accessible on the STA's CRT (i.e., summary will be continuously displayed). This top-level CSF summary has in fact been added to all CRT formats on MCB CRTs. as well as the STA's CRT. As such one activity ordered in the ASU3's Partial Initial Decision (See Item 2.(a) of the PID's Order) has been completed.
I 3.
Hydrogen Concentration and Containment Isolation l
Hydrogen concentration and a containment isolation summary status will be added to the lower-level display Critical Safety Function (CSF) status tree for the containment integrity CSF.
l Thus the top-lesel SPDS display of the containment integrity CSF will also consider challenges to integrity for hydrogen and containment isolation. In regards to containment isolation, NHY also intends to add another low-level display which will 1
provide more detailed information'concerning the status of con-tainment isolation. NHY will implement the changes prior to i-issuance of the full power license for hydrogen concentration and prior to startup following first refueling for containment isolation.
It should be noted that as described in thE FSAR, the hydrogen mon-itor is not functioning until the operator places it into operation from the normal standby condition. The low-level display will a
identify this normal standby condition as a black indication of the terminus exiting the hydrogen concentration logic box. This will also indicate that valid information is not available. This j
color code is consistent with the color coding scheme of the SPDS (i.e., black is used for insufficient data to evaluate). Once the operator places the hydrogen monitor into operation, as described in the FSAR, the logic box will return to an active i
state, and display information regarding hydrogen concentrations.
T b
+
- ATTACIDENT 1 TO NYN-87049 SAFETY PARAMETER DISPLAY SYSTEM RAIs (Continued) i 4.
Radiation Control Screin
\\
The low-level display radi.ation cSntrol screen will be functional prior to issuance of full po(ar li@ense. The top-level display 23
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will be changed so that this low-level display will feed the top-level, summary, matrix. ' This aJd4 tion to the top-level display f will be implemented prior to start-dp following first refueling.
N 5.
Resident Heat Removal Flow (EhK' Flew):
NHY is presently evaluating adding RHR to the appropriate lower-1evel display CSF scatus tree for either the core cooling or heat 4
s,
. These CSFs, however, may not be the best CSF fit from sink CSF.
- the operational, training, and procedural standpoint. In this e' vent NHY would propose an alternative acceptable to the Staff which would use existing /new high and low level displays. However, in any case, NHY will implement the required changes prior to issuance of the full power license.
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