LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187

Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187

ML110950150
Person / Time
Site:	Hope Creek
Issue date:	04/04/2011
From:	Duke P Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N11-0098
Download: ML110950150 (9)

Text

PSEG P.O. Box 236, Hancocks Bridge, NJ 08038-0236 OPSEG Nuclear LLC 10 CFR 50.90 LR-N11-0098 April 4, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187

References:

(1) Letter from PSEG to NRC, "Application for Technical Specification Change Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," dated March 19,2010 (ML100900224)

(2) Letter from NRC to PSEG, "Hope Creek Generating Station - Issuance of Amendment Re: Relocation of Specific Surveillance Frequencies to a Licensee Controlled Program Based on Technical Specifications Task Force (TSTF) Change TSTF-425 (TAC NO. ME3545)," dated February 25,2011 (ML103410243)

In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request (LAR H10-

01) for Hope Creek Generating Station (HCGS). The request would modify HCGS Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program, the Surveillance Frequency Control Program, with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk Informed Method for Control of Surveillance Frequencies."

In Reference 2 the NRC issued Amendment 187 approving the Reference 1 request.

The TS camera-ready pages prepared for LAR H10-01 and provided to the NRC contained format and typographical errors; Le., these errors were differences from the marked up TS pages provided in Reference 1. These errors were subsequently included in the revised TS pages issued with Amendment 187 (Reference 2). In Attachment 1 of this submittal PSEG is providing corrected pages that reflect the markups provided in Reference 1.

There are no regulatory commitments contained in this submittal.

Document Control Desk Page 2 LRmN11-0098 If you have any questions or require additional information, please do not hesitate to contact me at (856) 339-1466.

Sincerely,

~0.J2(l~

Paul R. Duke, Jr.

Licensing Manager - PSEG uclear Attachment

w. Dean - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek (X24)

P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG CommitmJmt Coordinator - Corporate".  :~" ..

LR-N11-0098 ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES WITH CORRECTED FORMAT AND EDITORIAL CHANGES:

Amendment 187 The following HCGS Technical Specifications pages (Facility Operating License NPF-57) are provided in this submittal:

3/42-1 3/4 3-7 3/43-29 3/43-30 3/43-39 3/46-10

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION 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 />.

SURVEILLANCE 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 UNIT CHECK(m) TEST (m) CALIBRATION (a) (m) SURVEILLANCE REQUIRED

1. Intermediate Range Monitors:

(b)

a. Neutron Flux - High r-~ 2 3,4,5

b. Inoperative NA NA 2,3,4,5

2. Average Power Range Monitor(f):

(b) (I)

a. Neutron Flux - Upscale, 2 Setdown 3,4,5

b. Flow Biased Simulated Thermal (9) (d) (e) (h)

Power-Upscale 1 (d)

c. Fixed Neutron Flux - Upscale 1

d. Inoperative NA NA 1,2,3,4,5

3. Reactor Vessel Steam Dome (k)

Pressure - High 1,2

4. Reactor Vessel Water Level - Low, (k)

Level 3 1,2

5. Main Steam Line Isolation Valve -

Closure NA 1

6. This item intentionally blank (k)

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

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CONDITIONS CHANNEL FUNCTIONAL CHANNEL FOR WHICH SURVEILLANCE TRIP FUNCTION CHECK (e) TEST (e) CALIBRATION (e) REQUIRED

4. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. RWCU !l Flow - High 1,2,3

b. RWCU !l Flow - High, Timer NA 1,2,3

c. RWCU Area Temperature - High NA 1,2,3

d. RWCU Area Ventilation !l Temperature - High NA 1,2,3 (b)

e. SLCS Initiation NA NA 1,2

f. Reactor Vessel Water Level- Low Low, Level 2 1,2,3 (a)

g. Manual Initiation NA NA 1,2,3

5. REACTOR CORE ISOLATiON COOLING SYSTEM ISOLATION

a. RCIC Steam Line !l Pressure (Flow) - High NA 1,2,3

b. RCIC Steam Line !l Pressure (Flow) - High, Timer NA 1,2,3

c. RCIC Steam Supply Pressure - Low NA 1,2,3

d. RCIC Turbine Exhaust Diaphragm Pressure - High NA 1,2,3

e. RCIC Pump Room Temperature - High NA 1,2,3 f RCIC Pump Room Ventilation Ducts !l Temperature - High NA 1,2,3

g. RCIC Pipe Routing Area Temperature - High NA 1,2,3

h. RCIC Torus Compartment Temperature -High NA 1,2,3

i. Drywell Pressure - High 1,2,3

j. Manual initiation NA NA 1,2,3 HOPE CREEK 3/43-29 Amendment No. 187

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CONDITIONS CHANNEL FUNCTIONAL CHANNEL FOR WHICH SURVEILLANCE TRIP FUNCTION CHECK (e) TEST (e) CALIBRATION (e) REQUIRED

6. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

a. HPCI Steam Line ~ Pressure (Flow) - High NA 1,2,3

b. HPCI Steam Line ~ Pressure (Flow) - High, Timer NA 1,2,3

c. HPCI Steam Supply Pressure - Low NA 1,2,3

d. HPCI Turbine Exhaust Diaphragm Pressure-High NA 1,2,3

e. HPCI Pump Room Temperature - High NA 1,2,3 f HPCI Pump Room Ventilation Ducts ~

Temperature - High NA 1,2,3

g. HPCI Pipe Routing Area Temperature - High NA 1,2,3

h. HPCI Torus Compartment Temperature -High NA 1,2,3

i. Drywell Pressure - High NA 1,2,3

j. Manual Initiation NA NA 1,2,3

7. RHR SYSTEM SHUTDOWN COOliNG MODE ISOLATION

a. Reactor Vessel Water Level - Low, Level 3 1,2,3

b. Reactor Vessel (RHR Cut-in Permissive)

Pressure - High NA 1,2,3

c. Manual Initiation NA (a)

NA 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 OPERATIONAL CONDITIONS CHANNEL FUNCTIONAL CHANNEL FOR WHICH SURVEILLANCE TRIP FUNCTION CHECK (a) TEST (a) CALIBRATION (a) REQUIRED

1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level- Low Low Low, Level 1 1,2,3,4*,5*

b. Drywell Pressure - High 1,2,3

c. Reactor Vessel Pressure - Low 1,2,3,4*,5*

d. Core Spray Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4*, 5*

e. Core Spray Pump Start Time Delay - Normal Power NA 1, 2, 3, 4*, 5*

f. Core Spray Pump Start Time Delay - Emergency Power NA 1,2,3,4*,5*

g. Manual Initiation NA NA 1,2,3,4*,5*

2. LOW PRESSURE COOLANT iNJECTION MODE OF RHR SYSTEM

a. Reactor Vessel Water Level- Low Low low, Level 1 1,2,3,4*,5*

b. Drywell Pressure - High 1,2,3

c. Reactor Vessel Pressure - Low (Permissive) 1,2,3,4*,5*

d. LPCI Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4*, 5*

e. LPCI Pump Start Time Delay - Normal Power NA 1,2,3,4*,5*

f. Manual Initiation NA NA 1,2,3,4*,5*

3. HiGH PRESSURE COOLANT INJECTION SYSTEM#

a. Reactor Vessel Water Level- Low Low, Level 2 1,2,3

b. Drywell Pressure - High 1,2,3

c. Condensate Storage Tank Level - low 1,2,3

d. Suppression Pool Water level - High 1,2,3

e. Reactor Vessel Water Level- High, Level 8 1,2,3

f. HPCI Pump Discharge Flow - Low (Bypass) 1,2,3

g. Manual Initiation NA NA 1,2,3 HOPE CREEK 3/43-39 Amendment No. 187

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" 90°,225°,90°,270° (under vessel)

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

c. 111'10"-139'2" 55°,240°,155°,315°

d. 139'2"-168'0" 45°,215°,00,90°,180°,270°

e. 168'0"-192'7" 95°, 130 0 , 300 0 , 355°, 45 0 , 225°

• At least one reading from each elevation zone is required for a volumetric average calculation.

HOPE CREEK 3/46-10 Amendment No. 187