ML110980151

Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425

ML110980151
Person / Time
Site:	Hope Creek
Issue date:	04/19/2011
From:	Richard Ennis Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Ennis R, NRR/DORL, 415-1420
References
TAC ME3545, TAC ME5981
Download: ML110980151 (9)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 19, 2011 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLG P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION - CORRECTION TO AMENDIVIENT NO. 187 REGARDING RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE-CONTROLLED PROGRAM BASED ON TECHNICAL SPECIFICATION TASK FORCE (TSTF) CHANGE TSTF-425 (TAC NO. ME5981)

Dear Mr. Joyce:

On February 25,2011, the Nuclear Regulatory Commission (NRC) issued Amendment No. 187 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station (HCGS)

(Agencywide Documents Access and Management System (ADAMS) Accession No. ML103410243). This amendment consisted of changes to the Technical Specifications (TSs) and Facility Operating License in response to your application dated March 19, 2010, as supplemented by letters dated July 28, 2010, and January 10, 2011 (ADAMS Accession Nos.

ML100900224, ML102230417, and ML110200059, respectively). The amendment modified the TSs by relocating specific surveillance frequencies to a licensee-controlled program based on TS Task Force (TSTF) Change TSTF-425.

By letter dated April 4, 2011 (ADAMS Accession No. ML110950150), PSEG Nuclear LLC (PSEG) informed the NRC staff that some of the TS camera-ready pages prepared by PSEG to support issuance of the amendment contained format and typographical errors. Corrected pages were provided in Attachment 1 to PSEG's letter. The NRC staff has reviewed the corrected TS pages and determined they are consistent with the proposed TS markups included in the application dated March 19, 2010. The specific corrections are as follows:

1) TS page 3/4 2 the word "thereafter" was added to Surveillance Requirement 4.2.1.a.

2) TS pages 3/4 3-7,3/43-29,3/43-30, and 3/43 spaces between some of the rows in each table were deleted so the information in the table aligns properly with the respective Functional Unit or Trip Function.

3) TS page 3/4 6 the degree symbol """ was added after the value "270" in Surveillance Requirement 4.6.1.7.d.

T.Joyce

-2 Enclosed are the corrected TS pages for HCGS Amendment No. 187. Please replace the affected pages in the HCGS TSs with the enclosed pages. If you have any questions, please contact me at 301-415-1420.

Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

As stated cc w/encl: Distribution via Listserv

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CQNDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 24% of RATED THERMAL POWER.

ACTION:

With an APLHGR exceeding the limits specified in the CORE OPERATING LIMITS REPORT, initiate corrective action within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 24% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

§URVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits specified in the CORE*

OPERATING LIMITS REPORT:

a.

Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is greater than or equal to 24% of RATED THERMAL POWER and in accordance with the Surveillance Frequency Control Program thereafter.

b.

Initially and in accordance with the Surveillance Frequency Control Program when the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.

HOPE CREEK 3/42-1 Amendment No. 187

TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNII CHECK (m)

TEST (m)

CALIBRATION (a) (m)

SURVEILLANCE REQUIRED

1.

Intermediate Range Monitors:

a.

Neutron Flux - High (b)

c.

2 3,4,5

b.

Inoperative NA NA 2.3.4,5

2.

Average Power Range Monitorfl:

(b)

(I)

a.

Neutron Flux - Upscale, 2

Setdown 3,4,5

b.

Flow Biased Simulated Thermal (9)

(d) (e) (h)

Power-Upscale 1

c.

Fixed Neutron Flux - Upscale (d) 1

d.

Inoperative NA NA 1,2.3,4,5

3.

Reactor Vessel Steam Dome Pressure - High (1<)

1,2

4.

Reactor Vessel Water Level - Low, Level 3 (1<)

1.2

5.

Main Steam Line Isolation Valve Closure NA 1

6.

This item intentionally blank

7.

Drywell Pressure - High (1<)

1,2 HOPE CREEK 3/43-7 Amendment No. 187

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP FUNCTION

4.

REACTOR WATER CLEANUP SYSTEM ISOLATION

a.

RWCU 6. Flow - High

b.

RWCU 6. Flow - High. Timer

c.

RWCU Area Temperature - High

d.

RWCU Area Ventilation 11 Temperature - High

e.

SLCS Initiation

f.

Reactor Vessel Water Level-Low Low, Level 2

g.

Manual Initiation

5.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a.

RCIC Steam Line t:. Pressure (Flow) - High

b.

RCIC Steam Line t:. Pressure (Flow) - High, Timer

c.

RCIC Steam Supply Pressure - Low

d.

RCIC Turbine Exhaust Diaphragm Pressure - High

e.

RCIC Pump Room Temperature - High f

RCIC Pump Room Ventilation Ducts 11 Temperature - High

g.

RCIC Pipe Routing Area Temperature - High

h.

RCIC Torus Compartment Temperature -High

i.

Drywell Pressure - High

j.

Manual Initiation CHANNEL CHECK (0)

CHANNEL FUNCTIONAL TEST (c)

CHANNEL CALIBRATION (c)

NA NA NA NA (b)

NA NA (a)

NA NA NA NA NA NA NA NA NA NA NA OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1,2.3 1.2,3 1.2.3 1,2,3 1,2 1,2,3 1,2,3 1,2,3 1.2,3 1,2.3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1.2,3 HOPE CREEK 3/43-29 Amendment No. 187

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP FUNCTION

6.

HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

a.

HPCI Steam Line Ll Pressure (Flow) - High

b.

HPCI Steam Line Ll Pressure (Flow) - High, Timer

c.

HPCI Steam Supply Pressure - Low

d.

HPCI Turbine Exhaust Diaphragm Pressure High

e.

HPCI Pump Room Temperature - High f

HPCI Pump Room Ventilation Ducts !J.

Temperature - High

g.

HPCI Pipe Routing Area Temperature - High

h.

HPCI Torus Compartment Temperature -High

i.

Drywell Pressure - High

j.

Manual Initiation

7.

RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a.

Reactor Vessel Water Level - Low, Level 3

b.

Reactor Vessel (RHR Cut-in Permissive)

Pressure - High

c.

Manual Initiation CHANNEL CHECK (e)

CHANNEL FUNCTIONAL TEST (e)

CHANNEL CALIBRATION (e)

OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED NA 1,2,3 NA NA 1,2.3 1,2,3 NA NA 1,2,3 1,2,3 NA NA NA NA NA NA 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2.3 NA NA (a)

NA 1.2,3 1.2,3 HOPE CREEK 3/43-30 Amendment No. 187

TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL TRIP FUNCTION CHECK (a)

1.

CORE SPRAY SYSTEM

a.

Reactor Vessel Water Level Low Low Low, Level 1

b.

DrywelJ Pressure - High

c.

Reactor Vessel Pressure - Low

d.

Core Spray Pump Discharge Flow-Low (Bypass)

e.

Core Spray Pump Start Time Delay - Normal Power NA

f.

Core Spray Pump Start Time Delay - Emergency Power NA

g.

Manual Initiation NA

2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM

a.

Reactor Vessel Water Level-Low Low Low, Level 1

b.

Drywell Pressure - High

c.

Reactor Vessel Pressure - Low (Permissive)

d.

LPCI Pump Discharge Flow - Low (Bypass)

e.

LPCI Pump Start Time Delay - Normal Power NA

f.

Manual Initiation NA

3.

HIGH PRESSURE COOLANT INJECTION SYSTEM#

a.

Reactor Vessel Water Level-Low Low. Level 2

b.

Drywell Pressure - High

c.

Condensate Storage Tank Level-Low

d.

Suppression Pool Water Level - High

e.

Reactor Vessel Water Level-High, LevelS

f.

HPCI Pump Discharge Flow-Low (Bypass)

g.

Manual Initiation NA CHANNEL OPERATIONAL CONDITIONS FUNCTIONAL CHANNEL FOR WHICH SURVEILLANCE TEST (a)

CALIBRATION (a)

REQUIRED 1,2,3,4*,5*

1,2,3 1,2,3,4*,5*

1,2,3,4*,5*

1,2,3,4*,5*

1,2.3,4*,5*

NA 1,2,3,4*,5*

1,2,3,4*,5*

1,2,3 1,2.3,4*.5*

1.2,3,4*,5*

1.2,3,4*,5*

NA 1,2,3.4*.5*

1,2.3 1,2.3 1,2.3 1,2,3 1,2.3 1,2,3 NA 1,2,3 HOPE CREEK 3/43-39 Amendment No. 187 I

CONTAINMENT SYSTEMS DRYWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.7 Drywell average air temperature shall not exceed 135°F.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the drywell average air temperature greater than 135°F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.7 The drywell average air temperature shall be the volumetric average of the temperatures at the following locations and shall be determined to be within the limit in accordance with the Surveillance Frequency Control Program:

Elevation Zone Approximate Azimuth*

a.

86'11"-112'8" (under vessel) 90°,225°,90°,270°

b.

86'11"-111'10" (outside of pedestal) 135°,300°,100°,190°

c.

111'10"-139'2" 55°,240°,155°,315°

d.

139'2"-168'0" 45°,215°,0°,90°,180°,270°

e.

168'0"-192'7" 95°,130°,300°,355°,45°,225° At least one reading from each elevation zone is required for a volumetric average calculation.

HOPE CREEK 3/46-10 Amendment No. 187

T.Joyce

- 2 Enclosed are the corrected TS pages for HCGS Amendment No. 187. Please replace the affected pages in the HCGS TSs with the enclosed pages. If you have any questions, please contact me at 301-415-1420.

Docket No. 50-354

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL 1-2 R/F RidsNrrDorlLpl1-2 Resource RidsNrrLAABaxter Resource RidsNrrPMHopeCreek Resource Ridsl\\lrrDorlDpr Resource RidsNrrDraApla Resource BBrady, NRR/DLRlRPB1 Sincerely, Ira!

Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation RidsOgcRp Resource RidsAcrsAcnw _MaiICTR Resource RidsNrrDirsltsb Resource RidsRgn 1 MailCenter Resource GHill,OIS AHowe, NRR/DRAIAPLA GWaig, NRR/DIRS/ITSB ADAMS Accession No: ML1;.,;1=0:::i:9:::i:80:=1=:5;.,;1=*:y=:v::=ia=e=m==ai==1 OFFICE LPL1-2/P PL1-2/LA NAME REnnis ABaxter

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