ML20211M240
| ML20211M240 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/03/1997 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20046D868 | List: |
| References | |
| NUDOCS 9710140099 | |
| Download: ML20211M240 (4) | |
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Decument Control D00k LR-N97628 i
Attcchment 4 1
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j REVISED TECHNICAL SPECIFICATION PAGES FOR LCR H97-05 i
9710140099 971003
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20 $AFETY L,lMIt$ aNO t,!M G 4G $AFETY system $ETT!4G$
21 $ AF(TY L,lMtT$_
NEsWAl, 8OWER Low pressure or !,2w Flow 2.1.1
- aERMAL 80wtR ins 11 mot escoed 25% of RATED THE W L PowtR witn tre l
reactor vessel steam come pressure less than 785 psig or core flow less than 10% of *ated ficw.
APPLICA8!LtTY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With THERMAL P N R exceeding 25% of RATED THERMAL POWER and the reactor vessel stens does pressure less than 785 psig or core flow less than 10% of rated ficw, be in at least HOT $HUTOOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with tM requirements of Specification 6.7.1.
\\l0 THERMAL, POWER. Hiah Pressure and Mich Flow l
2.1.2 The NINIMUM CRITICAL. POWER RATIO (MCPR) shall not be 1ess than tn two recirculation loop operation and shall not be less than M ith single recirculation loop operation, in both cases with the reactor vessel steam coes pressure greater than 785 psig and core flow greater than 105 of rated flow. N.
APPLICABILITY: OPERATIONAL CON 0!TIONS 1 and 2.
ACTION:
.go with MCPR less than th two recirculation loop operation or less than
> 1 8 with single recirculation loop operation and in both cases with the reactor vessel steam come pressure greater than 785 psig and core flow greater than 10%
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of rated flow, be in at least NOT SHUT 00WN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with the requirements of Specification 6.7.1.
REACTOR COOLANT $YSTDs PRESSURE 2.1.3 The esector coolant systes pressure, as measured in the reactor vessel steam done, sha)1 not anceed 1325 psig.
APPt,1C g t OPERATIONAL CONDITIONS 1, 2, 3 and 4.
ACT104:
o With the reacter coolant systes pressure, as esasured in the reactor vessel steam done, above 1325 psig, be in at least H0T SHUTDOWN with reactor coolant systes pressure less than er equal to 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and comply with 4
the requirements of Specification 6.7.1.
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O HOPE CREEK 2-1 Amendment No.15
e ADMINISTRATIVE CONTROLS sessessessenessesseeeeeeeeeen................................................
COPE OPERATIN3 LIMITS REPORT (Continued)
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by URC in UEDE 24011 P A (tne latest approved revisiond(* General Electric Standard Application for Reactor Fuel (CESTAR !!)
The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal mechanical limits, core thermal hydraulic limits, ECOS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CONE OPERATING LIMITS REPORT, including any mid cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL PEPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a ecpy to the USURC Administrator, Region 1, within the time period specified for each
- report, 6.9,3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a copy to the USNRC Administrator, Region 1, via l
the Licensee Event Report System within 30 days.
6.10 PECORD PETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
SPECIAL PEPORT.1 6.10.2 The following records shall be retained for at least 5 years a.
Records and logs of unit operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS submitted to the Commission, d.
Reccrds of surveillance activities, inspections, and calibrattens required by these Technical Specifications, Reccrds of changes made to the procedures required by specification e.
6.0.1.
f, Rec:rds of radioactive shipments.
Reccrds of sealed source and fission detector leak tests and results.
g.
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6-21 Amend ent Mc. 52 l r~
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4 Document Control D30k LR-N97628 Attochment 3 l
l NON-PROPRIETARY VERSION OF PSE&G LETTERS DATED JULY 16, 1997 AND-AUGUST 26, 1997 FOR PUBLIC DISCLOSURE i
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