ML20210U856
| ML20210U856 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/06/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N87016, NUDOCS 8702180615 | |
| Download: ML20210U856 (3) | |
Text
o d
Pubhc Service Electric and Gas Cornpany C rbin A. McNeill, Jr.
Public Service Electnc and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609 339-4800 vice President -
February 6, 1987 NLR-N87016 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL INFORMATION SINGLE LOOP OPERATION TECHNICAL SPECIFICATION HOPE CREEK GENERATING STATION DOCKET 50-354 Public Service Electric and Gas Company ( PSE&G ) hereby transmits supplemental information regarding the Hope Creek Generating Station (HCGS) Single Loop Operation (SLO) Technical Specification.
This transmittal supplements previous submittals from Mr. C. A. McNeill, Jr. (PSE&G) to Ms. Elinor G. Adensam (NRC) dated May 30, 1986, October 6, 1986 and December 24, 1986 and addresses recent discussions with members of the NRC staff.
Specifically, HCGS SLO Technical Specification Table 3.3.6-2, Control Rod Block Instrumentation Setpoints, includes a double asterisk footnote (**)
which clarifies applicability of the Source Range Monitor Downscale Trip Setpoint.
Since this footnote was developed for and used during the initial core loading only, the footnote should be removed in its entirety rather than annotated as shown in the December 24, 1986 submittal.
Therefore, Attachment 1 of this transmittal contains the referenced Technical Specification table as it appeared in the December 24, 1986 submittal with the modification discussion above.
This transmittal does not affect the determination that the requested SLO changes do not involve a significant hazards consideration (ref: May 30, 1986 submittal) as the attached modification can be considered editorial.
Should you have any questions or comments on this transmittal, do not hesitate to contact us.
Sincerely, 0702180615 870206 PDR ADOCK 05000354
/
I P
PDH f (j0l Attachment I
Document Control Desk 2
2/6/87 C
Mr.
D.
H. Wagner USNRC Licensing Project Manager Mr.
R.
W. Borchardt USNRC Senior Resident Inspector
l TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS k
TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE
[
1.
R00' BLOCK MONITOR
\\
g a.
Upscale
< '^ " " + 40%
< :. " 5 + 43%
g b.
Inoperative NA RA T
l Downscate
> 5% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER pgg c.
2.
\\
\\
l a.
Flow Biased Neutron Flux -
A
\\
Upscale
< = Z 2 + 42%*
. < =. 2 2 + 45%*
b.
Inoperative RA T
RA T
c.
Downscale
> 4% of RATED THERMAL POWER
> 3% of RATED THERMAL POWER d'.
Neutron Flux - Upscale, Startup i12%ofRATEDTHERMALPOWER
{14%ofRATEDTHERMALPOWER 3.
SOURCE RANGE MONITORS a.
Detector not full in NA NA 5
5 b.
Upscale
< 1.0 x 10 cps
< 1.6 x 10 cp, c.
Inoperative RA NA d.
Downscale
> 3 cp
> 1.8 cps 4.
a.
Detector not full in NA NA b.
Upscale
< 108/125 divisions of
< 110/125 divisions of Y
Tull scale Tull scale E
c.
Inop'erative NA NA l
d.
Downscale
> 5/125 divisions of
> 3/125 divisions of Tull scale Tull scale 5.
Water Level-High (Float Switch) 109'1" (North Volume) 109'3" (North Volume) 108'11.5" (South Volume) 109'1.5" (South Volume) 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale
< 108% of rated flow
< 111% of rated flow b.
Inoperative HA HA c.
Comparator i 10% flow deviation i 11% flow deviation 7.
REACTOR MODE SWITCH SHUTDOWN POSITION NA NA M
y 9
"The = :::rr : r r nn;: nn;q:. rod block function is varied as a function of recirculation loop flow 2
(W)) The trip setting of m function must be maintained in accordance with Specificatien 3.2.2.
a e t u s r i a n s n - -
i t
s_
gg MJXO7
~