ML040611009

Corrections to Technical Specifications

ML040611009
Person / Time
Site:	Seabrook
Issue date:	02/27/2004
From:	Nerses V NRC/NRR/DLPM/LPD1
To:	Peschel J, Warner M Florida Power & Light Energy Seabrook
References
Download: ML040611009 (17)

Text

NUCLEA UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 1, 2002 Mr. Ted C. Feigenbaum Executive Vice President and Chief Nuclear Officer North Atlantic Energy Service Corporation c/o Mr. James M. Peschel P.O. Box 300 Seabrook, NH 03874

SUBJECT:

ISSUANCE OF CONFORMING AMENDMENT - SEABROOK STATION, UNIT NO. 1 (TAC NO. MB6497)

Dear Mr. Feigenbaum:

By Order dated October 25, 2002, the U.S. Nuclear Regulatory Commission (NRC) approved the transfer of the license for Seabrook Station, Unit No. 1 (Seabrook Station), to the extent held by North Atlantic Energy Service Corporation (NAESCO), as the licensed operator of the facility, and certain co-owners of the facility, on whose behalf NAESCO was also acting, to FPL Energy Seabrook, LLC (FPLE Seabrook). The NRC also approved a conforming amendment.

These actions were taken pursuant to Sections 50.80 and 50.90 of Title 10 of the Code of Federal Regulations.

In a letter dated October 28, 2002, NAESCO informed the NRC that the closing for the sale of the relevant Seabrook Station ownership interests is scheduled to occur on November 1, 2002, and that all proposed selling owners will transfer their respective interests in Seabrook Station to FPLE Seabrook on that date. In a letter dated October 22, 2002, NAESCO notified the NRC that it was in receipt of all regulatory approvals other than the NRC's required for the license transfer. In a letter dated July 25, 2002, American Nuclear Insurers documented that FPLE Seabrook had obtained the appropriate amount of insurance required of licensees under 10 CFR Part 140 of the Commission's regulations.

Accordingly, the Commission has issued the enclosed Amendment No. 86 to Facility Operating License No. NPF-86 for Seabrook Station. The safety evaluation supporting the conforming amendment was enclosed with the Order issued on October 25, 2002.

T. Feigenbaum Enclosure 2 contains 13 copies of Indemnity Agreement No. B-106, Amendment No. 4, for Seabrook Station, which are required in connection with the transfer of the license. Please ensure that each of the 12 signatories receives an original copy of the Indemnity Agreement signed by all signatories and return the other original signed copy to the NRC.

Sincerely, IRAN Robert D. Starkey, Project Manager, Section 2 Project Directorate I Division of Ucensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

1. Amendment No. 86 to NPF-86

2. Indemnity Agreements cc w/encls: See next page

ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Facility Operating License with the attached revised pages.

The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Facility Operating License pages 1 through 6 Facility Operating License pages 1 through 7 Cover page for Appendix B Cover page for Appendix B Page 1 of Appendix C Page 1 of Appendix C

(4) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6) FPL Energy Seabrook, LLC, pursuant to the Act and 10 CFR 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein; and (7) DELETED C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FPL Energy Seabrook, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% of rated power).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

• and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No.

NPF-86. FPL Energy Seabrook, LLC, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) License Transfer to FPL Energy Seabrook. LLC

a. On the closing date(s) of the transfer of any ownership interests in Seabrook Station covered by the Order approving the transfer, FPL Energy Seabrook, LLC, shall obtain from each respective transferring owner all of the accumulated decommissioning trust funds for the facility, and ensure the deposit of such funds and additional funds, if necessary, into a decommissioning trust or trusts for Seabrook Station established by FPL Energy Seabrook, LLC, such that the amount of such funds deposited meets or exceeds the amount required under 10 CFR 50.75 with respect to the interest in Seabrook Station FPL Energy Seabrook, LLC, acquires on such dates(s).

• Implemented AMENDMENT NO. 86

August 27, 1 _

Docket No. 50-443 Mr. Ted C. Feigenbaum, Senior Vice President and Chief Nuclear Officer North Atlantic Energy Service Corporation Post Office Box 300 Seabrook, New Hampshire 03874

SUBJECT:

ISSUANCE OF AMENDMENT NO. 14 TO FACILITY OPERATING LICENSE NO.

NPF SEABROOK STATION, UNIT NO.. 1 (TAC NO. M83791)

The Commission has issued the enclosed Amendment No. 14 to Facility Operating License No. NPF-86 for the Seabrook Station. This amendment is in response to your application dated June 11, 1992.

This amendment would change the Seabrook Station Technical Specifications (TS) to implement the guidance of NRC Generic Letter (GL) 91-08, "Removal of Component Lists from Technical Specifications." The guidance of GL 91-08 is implemented by removing the listing of Secondary Containment Bypass Leakage Paths (Table 3.6-1) from TS. The listing of leak paths will instead be included in the Seabrook Technical Requirements Manual and the Final Safety Analysis Report (FSAR). Additionally, TS 3.6.3 is revised to permit locked or

.sealed closed containment isolation valves to be opened on an intermittent basis under administrative control..

A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly FEDERAL REGISTER notice. "

Sincerely, Original signed by Gordon E. Edison, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No. 14 to License No. NPF-86

2. Safety Evaluation cc w/enclosures:

See next page

i j

ATTACHMENT TO LICENSE AMENDMENT NO.14 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and

-c-ontain vertical lines indicating the area of change. Overleaf pages have

-teen provided.*

Remove Insert vii. vii

• viii viii 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 3/4 6-15 3/4 6-15I 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 B 3/4 6-3 B 3/4 6-3 B 3/4 6-4 B 3/4 6-4

PAGE INTENTIONALLY BLANK SEABROOK - UNIT 1 3/4 6-5 Amendment No.14

UNITED STATES NUCLEAR REGULATORY COMMiSSION WASHINGTON, D.C. 20555-0001 December 6, 1994 Mr. Ted C. Feigenbaum Senior Vice President and Chief Nuclear Officer North Atlantic Energy Service Corporation Post Office Box 300 Seabrook, NH 03874

SUBJECT:

CORRECTION TO AMENDMENT 33 TO FACILITY OPERATING LICENSE NPF-86 (TAC, M87849)

Dear Mr. Feigenbaum:

On November 23, 1994, the Commission issued Amendment 33 to Facility Operating License NPF-86 for the Seabrook Station, Unit No. 1. It has been brought to my attention that revised page 2-2 as issued did not include revised Figure 2.1-1. Please substitute the enclosed corrected copy of Page 2-2. For convienience, overleaf page 2-1 is included.

Sincerely, Albert W. De Agazio, Sr. P nager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-443 Serial No. SEA-94-028

Enclosure:

Corrected Page 2-2, Figure 2.1-1 to Amendment 33 cc w/encl: See next page

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T.,,) shall not exceed the limits shown in Figure 2.1-1 for four-loop operation.

APPLICABILITY: MODES 1 and 2.

Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and comply with the require-ments of Specification 6.6.

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION: -

MODES 1 and 2:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and comply with the requirements of Specification 6.6.

MODES 3, 4, and 5:

Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the requirements of Specification 6.6.

9412080232 941206 PDR ADDCK 05000443 P PDR SEABROOK - UNIT 1 2-1 Amendment No. 33

o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 r*sr September 11, 2003 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station PO Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE:

CHANGES TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH PRESSURE/TEMPERATURE LIMITS AND OVERPRESSURE PROTECTION SYSTEMS (TAC NO. MB6613)

Dear Mr. Warner:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 89 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No.

1, En response to your application dated october 11, 2002, as supplemented by letter dated May 29, 2003, filed by North Atlantic Energy Service Corporation (NAESCO) as the then licensee for Seabrook Station, Unit No. 1. On November 1, 2002, the NRC approved the transfer of the license for Seabrook Station, to the extent held by NAESCO, and certain co-owners of the facility, on whose behalf NAESCO was also acting, to FPL Energy Seabrook, LLC (FPLE Seabrook). By letter dated December 20, 2002, FPLE Seabrook requested that the NRC continue to review and act upon all requests before the Commission that had been submitted by NAESCO.

The amendment revises Technical Specification (TS) 3.4.9.1, "Reactor Coolant System

[RCS]-Pressure/Temperature Limits," and TS 3.4.9.3, "Reactor Coolant System - Overpressure Protection Systems," and their associated Bases sections. Specifically, the changes replace TS Figures 3.4-2 "Reactor Coolant System Heatup Limitations," 3.4-3 "Reactor Coolant System Cooldown Limitations," and 3.4-4 "RCS Cold Overpressure Protection," to allow operation to 20 Effective Full-Power Years.

The change also revises TS 3.4.9.3, Cold Overpressure Protection System, arming temperature from 329 'F to 290 "F. This change reflects the use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-641.

C .C

M.Warner A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, ictor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

1. Amendment No. 89 to NPF-86

2. Safety Evaluation cc w/encls: See next page

• *g C,

ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Insert vi vi x x xi xi 3/4 4-31 3/4 4-31 3/4 4-32 3/4 3-32 3/4 4-34 3/4 4-34 3/4 4-36 3/4 4-36 B 3/4 4-7 B 3/4 4-7 B 3/4 4-8 B 3/4 4-8 B 3/4 4-9 B 3/4 4-9 B 3/4 4-11 B 3/4 4-11 B 3/4 4-12 B 3/4 4-12 B 3/4 4-13 B 3/4 4-13 B 3/4 4-14 B 3/4 4-14 B 3/4 4-14a B 3/4 4-15 B 3/4 4-15

INDEX BASES - ..,

SECTION PAGE TABLE B 314A4-1 (THIS TABLE NUMBER IS NOT USED) ......................................... .... B 314 4-11 I 3/4A.10 STRUCTURAL INTEGRITY . ......................  ; B 314 4-16 314A.t11 REACTOR COOLANT SYSTEM VENTS...................................................... B 3/4 4-16 314.5 EMERGENCY CORE COOLING SYSTEMS 314.5.1 ACCUMUJLATORS......... B 3/4 5-1 34.5.2 and 314.5.3 ECCS SUBSYSTEMS ............... B 3/4 5-1 314.5.4 REFUELING WATER STORAGE TAK .......... B 3/4 5-2 314.6 CONTAINMENT SYSTEMS 314.6.1 PRIMARY CONTAINMENT ...... .... ... ...... . ...... B 3/4 6-1 314.62 DEPRESSURIZATION AND COOLING SYSTEMS .... .......................... B 314 6-3 314.6.3 CONTAINMENI ISOLATION VALVES ............................ ; B3146-3 314.6.4 COMBUSTIBLE GAS CONTROL ................ ..... .........  ;.; B 3/4 6-3 314.i.5 CONTAINMENT ENCLOSURE BUILDING.. . B 314 6-4 3/4.7 PLANTSYSTEMS 314.7.1 TURBINE CYCLE . . .........

.. ;.;..B314.7-1 3/4.7.2 STEAM GENERATOR PRESSURETEMPERATURE LMATON; ...................- : 34 73 314.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM ..................................... 3 7 314.7.4 SERVICE WATER SYSTEM ............ ....... .......... B3/47-3 314.7.5 ULTIMATE HEAT SINK. .i.;  : ;.; .;- -B 314 74 314.7.6 CONTROL ROOM SUBSYSTEMS ....................;;....0............ . B 3/4 7-4 314.77 SNUBBERS ....... .............. .................................................................... ;B 3/4 7-4 314.7.8 SEALED SOURCE CONTAMINATION .................................. ...... .. B 314 7-5 314.7.9 (HIS SPECIFICATION NUMBER IS NOT USED) ... ..... B 314 7-5 314.7.10 (rHIS SPECIFICATION NUMBER IS NOTUSED) ........ . B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 314.8.1,3/4.82, and 3M4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION ......... B 314 81 314.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .;;........................ B 314 8-3 314.9 REFUELING OPERATIONS 314.9.1 BORON CONCENtRATIO.N *................ B 3/4 9-1 314.9.2 INSTRUMENT10ATION ...  ;... ............. .. B 3/4 9-1 314.9.3 DECAYTIME ........ ............. ...... B 3/4 9-1 314.9A COMINMEN1 BUILDING PENETRAN11 ONS ................... B 3/4 9-1 314.9.6 COMMUNICATIONS ............... B 3/4 9-1 314.9.6 REFUELING MACHINE ..............  ;  ;.. B 314 9-1 314.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING ............................. B 3/4 9-2 SEABROOK - UNIT I A Amendment No. &6,C, 89

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 3, 2003 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT NO. I - ISSUANCE OF AMENDMENT RE:

RELOCATION OF TECHNICAL SPECIFICATIONS ASSOCIATED WITH BORATION SYSTEMS AND CHEMISTRY, AND REVISION OF SELECTED TECHNICAL SPECIFICATIONS ASSOCIATED WITH THE REACTOR COOLANT SYSTEM (TAC NO. MB6614)

Dear Mr. Warner:

The Commission has issued the enclosed Amendment No. 93 to Facility Operating License No.

NPF-86 for the Seabrook Station, Unit No. I (Seabrook), in response to your application dated October 11, 2002, filed by North Atlantic Energy Service Corporation (NAESCO), as the then licensee for Seabrook Station, Unit No. 1. On November 1, 2002, the U.S. Nuclear Regulatory Commission (NRC or the Commission) approved the transfer of the license for Seabrook, to the extent held by NAESCO, and certain co-owners of the facility, on whose behalf NAESCO was also acting, to FPL Energy Seabrook, LLC (FPLE Seabrook). By letter dated December 20, 2002, FPLE Seabrook requested that the NRC continue to review and act upon all requests before the Commission that had been submitted by NAESCO. FPLE Seabrook subsequently supplemented the application by letter dated May 29, 2003.

The amendment relocates Technical Specifications (TSs) Sections 3.1.2.1, "Reactivity Control Systems-Boration Systems-Flow Paths-Shutdown;" 3.1.2.2, "Reactivity Control Systems-Boration Systems-Flow Paths-Operating;" 3.1.2.3, "Reactivity Control Systems-Boration Systems-Charging Pumps-Shutdown;" 3.1.2.4, uReactivity Control Systems-Boration Systems-Charging Pumps-Operating;" 3.1.2.5, "Reactivity Control Systems-Boration Systems-Borated Water Sources-Shutdown;" 3.1.2.6, "Reactivity Control Systems-Boration Systems-Borated Water Sources-Operating;" and 3.4.7, uReactor Coolant System-Chemistry," to the Seabrook Station Technical Requirements Manual (SSTR). The amendment also revises TS 3.1.2.7, "Reactivity Control Systems-Boration Systems-isolation of Unborated Water Sources-Shutdown."

The amendment also revises TSs 3.4.1.2, "Reactor Coolant System-Reactor Coolant Loops and Coolant Recirculation-Hot Standby;" 3.4.3, "Reactor Coolant System-Pressurizer;" 3.4.7, "Reactor Coolant System-Chemistry;" and 3.9.2, "Refueling Operations-instrumentation," to adopt wording that more closely resembles NUREG-1431, Revision 2, "Standard Technical Specifications - Westinghouse Plants." The revision to TS 3/4.9.2 also involves surveillance changes. The associated Bases have been modified as a result of the changes.

M. E. Warner A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

1. Amendment No. 93 to NPF-86

2. Safety Evaluation cc w/encls: See next page C C - . . .

ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Insert iii iii v v x x 3/4 1-7 3/4 1-7 3/41-8 3/4 1-8 3/41-9 3/4 1-9 3/41-10 3/4 1-10 3/4 1-11 3/4 1-11 3/41-12 3/4 1-12 3/41-13 3/4 1-13 3/41-14 3/4 1-14 3/4 4-2 3/4 4-2 3/4 4-3 3/4 4-3 3/4 4-10 3/4 4-10 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 3/4 9-2 3/4 9-2 B 3/41-2 B 3/4 1-2 B 3/41-3 B 3/4 1-3 B3/44-1 B 3/44-1

---

B3/44-1a B 3/4 4-5 B 3/4 4-5 B 3/4 9-2a B 3/4 9-2a

---

B 3/4 9-2b

---

B 3/4 9-2c

---

B 3/4 9-2d

I REFUELING OPERATIONS 314.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE, each with continuous visual indication Inthe control room and one with audible Indication In the containment and control room.

APPLICABILITY: MODE 6.

ACTION:

a. With one of the above required monitors Inoperable or not operating, immediately suspend all operations Involving CORE ALTERATIONS or positive reactivity changes.

b. With both of the above required monitors Inoperable or not operating, Immediately initiate corrective action to restore one source range neutron flux monitor to OPERABLE status and determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I SURVEILLANCE REQUIREMENTS 4.92 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by, performance of:

a. A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. A CHANNEL CALIBRATION* at least once per 18 months. I

• Neutron detectors may be excluded from CHANNEL CALIBRATION. I SEABROOK- UNIT I 314 e-2 Amendment No. 93