ML20207Q936
| ML20207Q936 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/06/1987 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0896, RTR-NUREG-896 NYN-87026, NUDOCS 8703100243 | |
| Download: ML20207Q936 (3) | |
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-O George S. Thomas UI Vice Pre *MNuclear Production March 6, 1987 g
New Hampshire Yankee Division NYN-87026 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
References:
(a)
Facility Operating License NPF-56, Construction Permit CPPR-136, Docket Nos. 50-443 and 50-444 (b) NUREG-0896, Supplement No. 6, " Safety Evaluation Report Related to the Operation of Seabrook Station, Units 1 and 2", dated October, 1986 Subj ect:
Safety Parameter Display System (SPDS); Completed Activities Gentlemen:
New Hampshire Yankee (NHY) has completed activities identified in Section 18.2 of Reference (b) regarding the Seabrook Station SPDS. The Enclosure identifies the activities completed and briefly describes the action taken for each of these activities. As previously committed NHY will complete the remaining items (i.e., Items 2, 4, 8, 10, 11) prior to restart following first refueling.
NHY requests that resolution of these items be reflected in the next supplement to Seabrook Station's SER.
Should the Staff have any further questions regarding this matter, please contact the hHY Bethesda Licensing Office (Mr. R. E. Sweeney) at (301) 656-6100.
Very truly yours, 4*/C
/M Ceorge S. Thomas Enclosure cc: Atomic Safety and Licensing Board Service List Mr. Vincent S. Noonan, Director
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PWR Project Directorate No. 5 Division of PWR Licensing-A i
United States Nuclear Regulatory Commission g
Washington, DC 20555 l
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0703100243 870306M g 0500o443 PDR PDR
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O P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574 L
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ENCLOSURE TO NYN-87026 Completed SPDS Activities
- Item No. 1 Continuous display of the top-level critical safety function summary at the assigned SPDS control room location (i.e., STA's CRT).
Response
The top-level critical safety function summary.(1.e., overview color bar) has been added to all CRT formats accessible-on the STA's CRT (i.~e., summary will be continuously displayed).
Item No. 3 The containment isolation display is not satisfactorily readable from the
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prime SPDS location to be considered part of the SPDS.
Response
- The individual cells or indicators of the containment isolation display have been rearranged so the operators can determine by pattern recog-nition the overall status of containment isolation from the assigned SPDS location. As requested by the Staff, NHY will commit to maintaining or improving (when possible) the relative position and orientation of the j.
containment isolation display with respect to the assigned SPDS location.
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Item No. 5 Several human engineering discrepancies have been' identified.
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Response
1 This item concerns the heat sink format display and the lower-level display call-up method.-
In regards to the heat sink format display, the display format has been revised so that it is consistent with the labeling of other displays.
Concerning the call-up method, as recommended by the Staff, the display call-up method involves or requires only a single operator action.
- Activities keyed to the item numbers on Page 18-5 of SSER-6.
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ENCLOSURE TO NYN-87026 Completed SPDS Activities *
(Continued)
Item No. 6 Two CSF status trees are not mode dependent and have the potential for misleading the operator.
Response
This item concerns the subcriticality and core cooling status tree displays not being mode dependent.
The mode dependency enhancements to the subcriticality and core cooling status trees have been imple-mented. Therefore, these displays will not indicate the CSFs are being challenged during normal power operations.
Item No. 7 Isolation devices between the RVLIS and the SPDS have not yet been approved.
Response
Although identified as being open in Section 18.2 of SSER-6, NHY considers this item to be resolved based on technical evaluation reflected in Appendix 18A of SSER-6.
Item No. 9 The usefulness of the lower-level SPDS display formats to the operator is in question.
Response
The Staf f's concern involves the observation, during the site audit, of the operator /STA usage of the hard copy equivalent of the lower-level display format.
In resolution, NHY undertook a review to determine if there were any concerns with the display formats or the format's con-sistency with plant procedures.
This review did not identify any concerns or drawbacks with respect to the usefulness of the display formats. This review also determined that the display formats are consistent with the Seabrook Station emergency operating procedure sets. Furthermore, the hard copy status trees are identical to those displayed on the CRT. Therefore, no further action is required with regards to the lower-level display fo rma t s. NHY does intend to emphasize the usage of the CRT lower-level display versus the hard copy equivalent during operator / STA training sessions.
- Activities keyed to the item numbers on Page 18-5 of SSER-6..
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