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.            .                Decument Control D00k                                       LR-N97628 i                             Attcchment 4 1
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Attcchment 4 1
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j                                     REVISED TECHNICAL SPECIFICATION PAGES FOR LCR H97-05 i
j REVISED TECHNICAL SPECIFICATION PAGES FOR LCR H97-05 i
                                                            'n 9710140099  971003 AD0;K 05000354 PDR P                     PDR.                                                               -
9710140099 971003
'n PDR AD0;K 05000354 P
PDR.


1 1
20 $AFETY L,lMIt$ aNO t,!M G 4G $AFETY system $ETT!4G$
20 $AFETY L,lMIt$ aNO t,!M G 4G $AFETY system $ETT!4G$
21 $ AF(TY L,lMtT$_
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             !
NEsWAl, 8OWER Low pressure or !,2w Flow 2.1.1
10% of *ated ficw.
*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.
APPLICA8!LtTY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
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 hours and comply with tM requirements of Specification 6.7.1.
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 hours and comply with tM requirements of Specification 6.7.1.
THERMAL, POWER. Hiah Pressure and Mich Flow                                   \l0 l
\\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.
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.
APPLICABILITY: OPERATIONAL CON 0!TIONS 1 and 2.
ACTION:         .go with MCPR less than             th two recirculation loop operation or less than
ACTION:
            > 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%
.go with MCPR less than th two recirculation loop operation or less than
    \ .\ ?. of rated flow, be in at least NOT SHUT 00WN within 2 hours and comply with the requirements of Specification 6.7.1.
> 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%
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.
of rated flow, be in at least NOT SHUT 00WN within 2 hours 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.
APPt,1C g t OPERATIONAL CONDITIONS 1, 2, 3 and 4.
ACT104:
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 hours and comply with     4 the requirements of Specification 6.7.1.
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 hours and comply with 4
m v.                           <          .c CM Nel cf/L A\e h C de T ofer A .,                                 O M 7.
the requirements of Specification 6.7.1.
2-1                     Amendment No.15 HOPE CREEK
m v.
.c CM Nel M
cf/L A\\e h C de T ofer A.,
7.
O HOPE CREEK 2-1 Amendment No.15


e
e ADMINISTRATIVE CONTROLS sessessessenessesseeeeeeeeeen................................................
            .                            ADMINISTRATIVE CONTROLS sessessessenessesseeeeeeeeeen.......... ......................................
COPE OPERATIN3 LIMITS REPORT (Continued)
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                                                                                                                                                                       l approved revisiond(* General Electric Standard Application for Reactor Fuel (CESTAR !!)
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 core operating limits shall be determined so that all applicable limits (e.g.,
The CONE OPERATING LIMITS REPORT, including any mid cycle revisions or                                                                                                                                                                           !
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.
supplements thereto, shall be provided upon issuance, for each reload cycle,                                                                                                                                                                     ,
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.
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
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.
: 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.
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
SPECIAL PEPORT.1 6.10.2 The following records shall be retained for at least 5 years a.
: a.           Records and logs of unit operation covering time interval at each power level.
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.
b.
: c.           All REPORTABLE EVENTS submitted to the Commission,
Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
: d.           Reccrds of surveillance activities, inspections, and calibrattens required by these Technical Specifications,
c.
: e.            Reccrds of changes made to the procedures required by specification 6.0.1.
All REPORTABLE EVENTS submitted to the Commission, d.
f,           Rec:rds of radioactive shipments.
Reccrds of surveillance activities, inspections, and calibrattens required by these Technical Specifications, Reccrds of changes made to the procedures required by specification e.
: g.            Reccrds of sealed source and fission detector leak tests and results.
6.0.1.
s R EE t".                                                                                                         6-21                                                                             Amend ent Mc. 52 l c                                                                            -                                r~
f, Rec:rds of radioactive shipments.
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Reccrds of sealed source and fission detector leak tests and results.
                                            %                  $4                                                         e n         ,
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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
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
l NON-PROPRIETARY VERSION OF PSE&G LETTERS DATED JULY 16, 1997 AND-AUGUST 26, 1997 FOR PUBLIC DISCLOSURE i
                                                                                      )
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Latest revision as of 21:49, 5 December 2024

Proposed Tech Specs Pages Associated W/Slmcpr Changes
ML20211M240
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 10/03/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML20046D868 List:
References
NUDOCS 9710140099
Download: ML20211M240 (4)
v • d • e


Text

_ - _ _ _. - _. _. _. -

-_____._m.m__._..-.

4 1

Decument Control D00k LR-N97628 i

Attcchment 4 1

4 i

t i

i 4-i a

I i

i i

4 I

h

}

j REVISED TECHNICAL SPECIFICATION PAGES FOR LCR H97-05 i

9710140099 971003

'n PDR AD0;K 05000354 P

PDR.

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%

\\.\\ ?.

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.

m v.

.c CM Nel M

cf/L A\\e h C de T ofer A.,

7.

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.

s R EE t".

6-21 Amend ent Mc. 52 l r~

c oO b b A$ dd6 %/ 8. k C t'\\

th (

A fA n

\\Jaid Q a p k g'

$4 e

n

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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