ML20236F117
| ML20236F117 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/25/1998 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20236F114 | List: |
| References | |
| NUDOCS 9807020032 | |
| Download: ML20236F117 (3) | |
Text
7 Dccument Control Dock LR-N98277 Attcchm:nt 3 LCR H98-03 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS.TO THE TECHNICAL SPECIFICATIONS (TS)
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES L
The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this change request:
Technical Specification Page 4.4.2.1 3/4 4-8 4.5.1.d.2.b 3/4 5-5 l'
!-o 9807020032 990625 PDR ADOCK 05000354~
P PDR L.
REACTOR C00UUfT SYSTEM
^
SURVEILLANCE REQUIREMENTS 4.4.2.1c The acoustic monitor for each safety / relief valve shall be demonst sted OPERABLE with the setpoint verified to be s 30% of full open noise leve by performance of a:
CHAl#lEL FUNCTIONAL TEST at least once per 31 days, and a a.
b.
CHANNEL CALIBRATION at least once per 18 month 4.4.2.2 At least 1/2 of the safety relief valve pilot stage assemblies shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 18 months, and they shall be rotated such that all 14 safety relief valve pilot stage assemblies are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 40 months.
4.4.2.3 The safety relief valve main (mechanical) stage assemblies shall be set pressure tested, reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's rectamendations at least once every 5 years.
Mnrp. vii si=: Mi ification 4.0.4 are not applicable _provided-th Surveillance is,perfo Mn* hr:=tfier feactor steam pressure is w
adeaumta te p.... sne test.
- Iriitial setYtii ehl! " in accordance with t e==~#::te,.c^s recommendations. Adjus+=an h t?
noise level shall be ace-F t:hd.iier the initial noise traces have been ana m
l HOPE CREEK 3/4 4-8 Amendment No. 64
EMERGENCY CORE "00L*NG SYSTEMS 50RVEILLANCEREOUIREMENTS(Continuea) 2.
For the HPCI system. verifying that:
1)
The system aevelops a flow of at least 5600 gpm against a test line oressure corresponding to a reactor vessel pressure of 200 psig, wnen steam is being supplied to the turoine at 200 + 15, -0 psig.**
3)
The suction is automatically transferred from the condensate storage tank to the suppression enameer on a condensate storage tank water level - low signal and on a sucoression namber water level ligh signal.
(
3.
Performing a CHANNEL CALIBRATION of the CSS, and LPCI system I
- lischarge line " keep filled" alarm instrumentation.
4 Derforming a CHANNEL CALIBRATION of the CSS header IP instruments-tion and verifying the setooint to be i t5e allowable value of 4.4 psid.
{
5.
Performing a CHANNEL CALIBRATION of the LPCI header AP instrumen-tation and verifying the setpoint to be i the allowable value of 1.0 psid.
d.
For the ADS:
1.
At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the Primary Containment Instrument Gas System low-low pressure alarm system.
2.
At least once per 18 months:
a)
Performing a system functional test which includes simulatec automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.
d "'b b)
WU fdC
- ally opening each ADS valve when the reactor steam dDme-pressu rester than or equal to 100 psig** nd '
Gru*<de 405 observing tha r:
+V ^^
1)
The control valve or alve position responds vhe si W accordingly, or b Dj" O
2)
Th acorrespondingchangeinthemesureQteam c)
Performing a CHANNEL CALIBRATION of the Primary Containment Instrument Gas System low-low pressure alarm system and verifying an alarm setpoint of 85 + 2 psig on decreasing pressure.
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
I HOPE CREEK 3/4 5-5 Amendment No. 35 Y
_ _ _ _