ML20154B339
| ML20154B339 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 02/27/1986 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-86-4, NUDOCS 8603040280 | |
| Download: ML20154B339 (2) | |
Text
.,.
i SNUPPS
' 3 pander $aed Nomeet Unit Power Mont Syveem 5 No Nry 8%ed Nichofes A.Patrica a.4,w, u.,vs.ns ww February 27,1986 E Ascutive Director (Jen eesocie SLNRC 66-4 FILE: J-111/0278 SUBJ: Plant Safety Par.weter Display Systern Verification and Validation Prograre Completion Mr. Harold R, Denton, Director Office of Nuclear Reactor Rsgulati6n
'J.$. Nuclear Regulatory Commission
'dashingten, D.C.
20555 i
Docket Nos.:
STN W482.and STN 50-483
Dear Mr. Denten:
J The purpose of thf s letter is twofold: first, to inform the NRC that the verification and validation (V&y) progran for the Safety Parameter 01 splay l
$ystem (SPDSJ at the SWFPS plants, Callaway Plant Unit No. I and Wolf j
Cre6k Generating Station Unit.No.1, has been successfully coutpleted, and 56cond, to clarify three tssues previously discussed with the NRC.
J V&V Prcgran Compl6 tion
/
i On May 22, 1985, mem.bers of the SNDPPS Utitities and SNUPPS Staff me' with the NRC staff 7.0 discuss staff coocerns regarding the SNUPPS SPDS.
Chapter I.D.2 " Plant Safety Paracieter Display System", extracted from Wolf Creek's SSER 5, formed the basis for these discussions.
Based on requests by the NRC staff, three of the -slides prepared by the SHUPPS Utilities and SN'JPPS Staff for use darfrg the presentation are attached and will te discussed below. Conclusions reached during this meGtJng indicated that i
the MC should be able to accept the SNUPPS SPDS subject to completica of i
the V&Y program, Now that the V&V program is complete, the hardware and j
software requirements for an SPDS at both SNUPPS plants is considered to be satisfied. Docuraentation regarding the V&V program is available for i
NRC inspection.
i Issue Clarification
)
1.
Validation Case Selection Scenarios which were used as part of the SPDS validation fr.cluded the following:
e large Loss of Cooter.t Accident (LOCA) i e Loss of main fesdwater e Core power excursion Steam generator tube rupture with loss of offsite power e
e Large steamline treak e A beyond-Design Basis scenario 1.e, t.0CA with inadequate, core cooling and fuel damage
\\,
m3 Tan 4 42
$o P
S
s
/
SLNRC 86-4 Page Two At least one scenario included specific criteria that demonstrated assessment of radicactivity control in an isolated steam generator; this commitment was made to the NRC on May 22, 1985.
2.
Sten Generator and Steamline Radiation Monitoring in Verification and Validation Program The SPDS has no additional monitoring capability for isolated steam generators beyond that currently provided for in the control room.
To determine radiation levels in the secondary side of the steam generator, it is necessary to obtain samples from the stean gene-rator blowdown lines.
3.
Containment Isolation Cor.tainment isolation indication on the SPDS is unnecessary because the SNUPPS design incorporates an Engineered Safety Features Status Panel which is the primary source of information used to determine containment isolation status of individual vhlves and systems. The panel is conveniently located on the main contro? board and easily observed from any point within the control room proper.
Very,truly yours, p-._ / y
-EL%-T\\C 0
N. A. Petrick DJK/jal/20b10
^
Attachments cc:
J. M. Evans KCPL G. L. Koester.KGE D. F. Schnell UE J. E. Cummins USNRC/WC E. H. Johnson USNRC/ Reg. IV B. Little USNRC/ CAL G. C. Wright USNRC/ Reg. III