ML12207A504

Issuance of Amendment for Adoption of TSTF-306

ML12207A504
Person / Time
Site:	Fermi
Issue date:	08/29/2012
From:	Mahesh Chawla Plant Licensing Branch III
To:	Jennifer Davis Detroit Edison, Co
Chawla M
References
TAC ME7720
Download: ML12207A504 (17)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 29, 2012 Mr. Jack M. Davis Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

FERMI 2 - ISSUANCE OF AMENDMENT FOR ADOPTION OF TSTF-306 (TAC NO. ME7720)

Dear Mr. Davis:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 189 to Facility Operating License No. NPF-43 for the Fermi 2 facility. The amendment consists of changes to the technical specifications (TSs) in response to your application dated December 20,2011 (Agencywide Documents Access and Management System (ADAMS)

Access No. ML113550138).

The amendment revises TSs requirements related to primary containment isolation instrumentation. The changes are in accordance with NRC-approved Technical Specification Task Force (TSTF), Improved Standard Technical Specifications (ISTS) change TSTF-306, Revision 2.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosures:

1. Amendment No. 189 to NPF-43

2. Safety Evaluation cc w/encls: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.189 License No. NPF-43

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (DECo, the licensee) dated December 20,2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

-2 Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.189, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. DECo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

)

/

(

Istvan Frankl, Acting Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 29, 2012

ATTACHMENT TO LICENSE AMENDMENT NO.189 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT License Page 3 License Page 3 3.3-50 3.3-50 3.3-53 3.3-53 3.3-55 3.3-55 3.3-56 3.3-56 3.3-57 3.3-57 3.3-58 3.3-58 3.3-58a

- 3 (4)

DECo, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material such as sealed neutron sources for reactor startup, sealed sources for reactor instrumen tation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

DECo, pursuant to the Act and 10 CFR Parts 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; and (6)

DECo, pursuant to the Act and 10 CFR Parts 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.

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 DECo is authorized to operate the facility at reactor core power levels not in excess of 3430 megawatts thermal (100%

power) in accordance with conditions specified herein and in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.189 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. DECo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Antitrust Conditions DECo shall abide by the agreements and interpretations between it and the Department of Justice relating to Article I, Paragraph 3 of the Electric Power Pool Agreement between Detroit Edison Company and Amendment No.189

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS

... ----. -.. -. -----. ---------. ---. --. -NOTES* --.. -. ---------. ----... -----. -.. --

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more requi red A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable.

---

NOTE-*--------

With a Table 3.3.6.1-1 Function 5.c channel ino~rable, isolation capability is considered maintained~rOVided Function 5.b is OPE BLE in the affected room.

B.l trip.

Restore isolation capabil i ty.

Functions 1. f.

2.a. 2.c, 6.b, 7.a. and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1.f, 2.a, 2.c, 6.b, 7.a, and 7.b 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.

One or more automatic Functions with isolation capability not maintained.

(continued)

FERMI - UNIT 2 3.3-50 Amendment No.

,~~, +/-7J 189

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

....... -.. -... -. -.. -.. -....... --. -...NOTES ------.. -.. -..... -. --. ---... ---. --..

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances. entry into associated Conditions and Required Actions may be delayed for up to:

a. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Function 5.8 when testing non-redundant circuitry that results in loss of isolation capability associated with this Function, provided Functions S.b, S.c, and S.e are OPERABLE;

b. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function S (other than non-redundant circuitry of S.a) provided the associated Function maintains isolation capability.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function S.C provided Function 5.b is OPERABLE in the affected room;

c. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1.2. 6.and 7, provided the associated Function maintains isolation capability; and

d. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for Functions 3 and 4, provided the associated Function maintains isolation capability.

SURVEILlANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3 Verify the trip unit setpoint.

92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months SR 3.3.6.1.6 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued)

FERMI. UNIT 2 3.3-53 Amendment No. J~~, +/-73 189

-I

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1*1 (~age 1 of 5)

Primary Containment Isola ion Instrumentation APPLICABLE t400ES OR REQUIRED C{JN!)moos REFERENCED OTHER CHANNELS fR{J!

FUNCTIOO SPECIFIED CONDITIONS PER TRIP SYSTEM REQUIRED ACTION C.l SIJMIllANCE REQUIREMENTS ALLOWABLE VALUE

1. Main Steam line Isolation j

a. Reactor Vessel Water Level -Low low Low.

Level 1 1.2,3 2

D SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7

~ 24.8 inches

b. Hain Steam line Pressure -Low 1

2 E

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 736 ps1g

c. Main Steam line Flow-High 1.2.3 2~r D

SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7

s: 118.4 psid

d.

Condenser "Pressure-High I,

2(a), 3(a) 2 D

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 s 7.05 psia

e. Main Steam Tunnel Teq>erature-High 1.2.3 2 per trip string D

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3:6.1.5

206'f

f. Main Steam line Radiation-High 1.2.3 2

0 SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5

s; 3.6 x full power background

g. Turbine Building Area Temperature-High 1.2.3 4

0 SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

s; 206c F

h.

Manual Initiation 1.2.3 1 rvr va ve G

SR 3.3.6.1.6 NA (continued)

(a) Except when bypassed during reactor shutdown or'for reactor startup under admnnistrative control.

FERMI - UNIT 2 3.3-55 Amendment No. l34 189

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1'1 (~age 2 of 5)

Primary Containment Isola ion Instrumentation APPLICABLE CONDlTlONS MODES OR REQUIRED REFERENCED FUNCTION OTl£R SPECIFIED COODITI(t4S OWlNELS PER TRIP SYSTEM FRJ)!

REQUIRED ACTIOO C.1 S\\JRVEIL~CE REtl.IIREMEJjTS ALLOWABLE VALUE

2. Primary Containment Isolation

a.

Reactor Vessel Water Level Low. Level 3 1.2.3 2

H SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 171. 9 inches

b.

Reactor Vessel water Level-Low. Level 2 1.2.3 2

H SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 103.8 inches

c. Orywell Pressure-High 1.2.3 2

H SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 1.88 pslg

d.

Manual Initiation 1.2.3 1 rvr va ve G

SR 3.3.6.1.6 NA

3. High Pressure Coolant Injection (HPCI) System Isolation

a.

HPC I Steam Li ne Flow-High 1.2.3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 410 inches of water with time delay 2: 1 second. and

~ 5 seconds

b.

HPCI Steam Supply Line Pressure-Low 1.2.3 2

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 2: 90 psig

c.

HPCI Turbine Exhaust Diaphragm Pressure -High 1,2.3 2

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 S; 20 psig

d.

HPCI EquiplllE!nt Room Temperature-Hi gh 1.2.3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 162"F

e. Drywell Pressure-High 1.2.3

'. 1 F

SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 s 1.88 psig

f. Manual Initiation 1.2,3 1 rvr va ve SR 3.3.6.1.6 NA (continued)

FERMI UNIT 2 3.3-56 Amendment No..}M, 189

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1'1 (page 3 of 5)

Primary Containment Isolation Instrumentation APPLICABLE COtillTIONS HODES ffi REQUIRED REFERENCED OTHER CHANNELS FRGI fllHCTION SPECIFIED COODITI!l6 PER TRIP SYSTEM REQUIRED ACTION C.1 SURVEILlANCE REQUIREMENTS AllOWABLE VALUE

4. Reactor Core Isolation Cooling (RCIC) Syste~

Isolation

a.

RCIC Ste~ line Flow-High 1.2.3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

s: 95.U inches of water with time delay

.<'! 1 second and s 5 seconds

b.

RCIC Steam Supply Line Pressure-Low 1.2,3 2

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

.<'! 53 psig

c. ReIC Turbine Exhaust Diaphragm Pressure - Hi gh 1.2,3 2

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 s 20 psig

d.

ReIC Equipment RoOlll Temperature-High 1,2,3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

s 162°F

e. Drywell Pressure-High 1.2.3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 S. 1.88 psi9

f. Manual Initiation 1.2,3 1 ~er va ve G

SR 3.3.6.1.6 NA (continued)

FERMI - UNIT 2 3.3-57 Amendment No. +/-34 189

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1'1 (~age 4 of 5)

Prilll1lry Containment Isola ion Instrumentation APPLICABLE COl{)IIIOtIS MODES OR REQUIRED REFERENCED imlER CHNINELS FRat SPECIFIED PER TRIP REQUIRED smVEILLANCE AlLOWMlLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIRDIENTS VALUE

5. Reactor Water Cleanup (RWCU) System Isolat1on

a. Differenti a 1 Flo.... - High 1.2.3 1

F SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 s 63.4 9JlIII

b. Area Temperature High 1.2.3 1 per area F

SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 s 183"F

c. Area Ventilation Di fferenti a 1 Temperature High 1.2.3 (d) f SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 s 53"F

d.

SLC System Initiation 1,2 2\\0)

I SR 3.3.6.1.5 NA

e. Reactor Vessel Water level - low Low.

level 2 1.2.3 2

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5

~ 103.8 inches

f. Manual Initiation 1.2.3 1 ~r va ve G

SR 3.3.6.1.6 NA

6. Shutdown Cooling System Isolation

a. Reactor Steam Dome PresslJre - Hi gh 1.2.3 1

F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 s 95.5 pSig

b. Reactor Vessel Water Level Low. Level 3 3.4.5 2(e)

J SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 O! 171.9 inches

c. Manual Initiation 1.2.3 1 ~er va ve G

SR 3.3.6.1.6 NA (continued)

(b)

SlC System Initiation only inputs into one of the two trip systems.

(c)

Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

(d)

For Function S.c, Reactor Water Cleanup (RWCU) System Isolation. Area Ventilation Differential Temperature - High. the required channels is 1 per rOOlll.

FERMI - UNIT 2 3.3-58 Amendment No. ~ft. m 189

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1*1 (page 5 of 5)

Primary Containment-Isolation Instrumentation APPLICABLE CONDITIONS HIDES 00.

ornER REQUIRED CHANNELS REFRENCED FIl:OH flJICTION SPECIFIED COOITI(ItS PER 1RIP SYSTEM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALL!XtIABLE VAlUE

7. Traversing In-core Probe Isolation

a. Reactor Vessel Water Level-Low, Level 3 1.2.3 2

G SR SR SR SR SR

b. Drywe11 Pressure - Hi gh 1.2.3 2

G SR SR SR SR SR 3.3.6.1.1

,

171. 9 inches 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 3.3.6.1.1

~ 1.88 psig 3.3.6.1.2 3.3.6.1.3 3.3.6.1.4 3.3.6.1.5 FERMI - UNIT 2 3.3*58a Amendment No. 189

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.189 TO FACILITY OPERATING LICENSE NO. NPF-43 DETROIT EDISON COMPANY FERMI 2 DOCKET NO. 50-341

1.0 INTRODUCTION

By letter dated December 20, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113550138), Detroit Edison (the licensee) requested an amendment to Operating License NPF-43 for Fermi, Unit 2 (Fermi 2). The proposed amendment would modify technical speCifications (TSs) requirements related to primary containment isolation instrumentation in accordance with the U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF), Standard Technical Specifications Change Traveler, TSTF-306, Revision 2, "Add action to Limiting Condition for Operation (LCO) 3.3.6.1 to give option to isolate the penetration" (ADAMS Accession No. ML003725864). The proposed amendment would revise TS Section 3.3.6.1, "Primary Containment Isolation Instrumentation," by adding an ACTIONS note allowing intermittent opening, under administrative control, of penetration flow paths that are isolated. Additionally, the traversing in-core probe (TIP) system would be added as a separate isolation function with an associated Required Action (Condition G) to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than immediately initiating a unit shutdown (Condition H).

2.0 REGULATORY EVALUATION

The NRC staff considered the following regulatory requirements and guidance in its review of the application: (1) The criteria for inclusion of LCOs in the TSs in Section 50.36 of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) and (2) TSTF-306, Revision 2.

Section 50.36(c)(2)(i) of 10 CFR Part 50 states that the TS will contain LCOs that "are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the condition can be met." The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated design-basis accidents (DBAs). Primary containment isolation within the

- 2 time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analysis for a DBA. The TIP system isolation ball valves, which are only open when the TIP system is in use, receive isolation signals from the Primary Containment Isolation Function, as specified in Table 3.3.6.1-1, Function 2.a (Reactor Vessel Water Level - Low Level 1), and 2.b (Drywell Pressure - High) of the TS. As such, an inoperability of the Primary Containment Isolation Function affecting only the TIP instrumentation would require a unit shutdown.

Isolation of the TIP system penetration flow paths in a design~basis event is assumed to be accomplished by manually actuating the shear (squib) valves.

3.0 TECHNICAL EVALUATION

TSTF-306, Revision 2, was submitted to the NRC on June 20,2000, and was made available for plant-specific adoption via incorporation into Revision 2 of the Standard Technical Specifications (STSs), NUREGs 1430-1434 on June 30, 2001. The licensee's proposal is consistent with the intent of TSTF-306, Revision 2.

3.1 Proposed TS Changes

The licensee proposes the following changes to Fermi 2, TS 3.3.6.1, "Primary Containment Isolation Instrumentation":

1. Adds a Note 1 to the Actions Notes that states "Penetration flow paths may be unisolated intermittently under administrative controls." An "s" is added to "NOTE" and the existing note becomes Note 2.

2. Revises the Completion Time of Condition A from "12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 1.f, 2.a, 2.c, and 6.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1.f, 2.a, 2.c, and 6.b" to "12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 1.f, 2.a, 2.c, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1.f, 2.a, 2.c, 6.b, 7.a and 7.b."

3. The TIP system isolation will be added as a separate isolation Function (7) in Table 3.3.6.1-1, with Function 7.a, "Reactor Vessel Water Level-Low, Level 3" and 7.b, "Drywell Pressure - High."

4. Adds Function 7 to Surveillance ReqUirements (SR) Note 2.c to allow delaying entry into associated Conditions and Required Actions for six hours when placing a channel in an inoperable status solely for performance of required surveillances.

3.2 Evaluation of Change TS 3.3.6.1 currently requires a unit shutdown in the event of an inoperability of the TIP instrumentation. The licensee is proposing to allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to isolate the affected TIP penetration flow paths. In addition, the proposal would allow intermittent opening, under administrative control, of penetration flow paths that are isolated. The proposed amendment would also modify the TS Bases to describe the proposed changes and provide supporting information. In its submittal, the licensee indicated that TSTF-306, Revision 2, serves to provide consistency between the requirements for equipment (TS 3.6.1.3, "Primary Containment

- 3 Isolation Valves (PCIVs)") and the instrumentation that supports the equipment and additional flexibility in the performance of maintenance and repair activities.

Prior to the approval of TSTF-306, Revision 2, STS 3.3.6.1, "Primary Containment Isolation Instrumentation," would not allow intermittent opening, under administrative controls, of penetration flow paths isolated due to inoperable primary containment isolation instrumentation and would require a shutdown in the event of an inoperability of the TIP instrumentation.

TSTF-306, Revision 2, revised STS 3.3.6.1 and its associated bases to be consistent with requirements of STS 3.6.1.3, "Primary Containment Isolation Valves," with respect to administratively opening isolated penetration flow paths and to be consistent with the Actions in STS 3.3.6.1 for inoperable manual isolation functions. The Actions for the Fermi 2 TS 3.3.6.1 would be modified by the addition of a Note allowing intermittent opening, under administrative control, of penetrations that are isolated to comply with Actions, SRs, or operating conditions.

These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. The primary containment isolation instrumentation serves as a support system for the PCIVs. Current Fermi 2 TS 3.6.1.3 contains an Actions Note that allows penetrations isolated due to Actions, SR, and operating conditions to be intermittently opened under administrative control. The accident consequences are not affected by the allowance of isolated penetrations to be intermittently opened under administrative control due to an inoperable PCIV of its associated instrumentation. Since the Actions for inoperability of the instrumentation need not be more restrictive than the inoperability of the function it supports, the addition of Action Note 1 is acceptable.

The Fermi 2 TS 3.3.6.1 would be further modified by adding the TIP system isolation as a separate isolation instrumentation Function with an associated Required Action to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than having to immediately initiate a unit shutdown. TIP system isolation in a design-basis event (with a loss of offsite power) would be accomplished by manual actuation of the shear valves. Additionally, the Actions for inoperable primary containment isolation instrumentation that requires a unit shutdown are overly restrictive in the event that the inoperability affects only the TIP isolation instrumentation. The proposed Action for the inoperability of this Function is the same as for inoperable manual isolation Functions (i.e., isolate the penetration in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />). This is because the TIP system penetration is a small bore (approximately %-inch), and its isolation in a design-basis event is via the manually operated shear valves. The ability to manually isolate the TIP system by either the normal isolation valve or the shear valve isolation provides an appropriate level of safety. Therefore, the NRC staff finds the proposed changes acceptable and consistent with the STS and TSTF-306, Revision 2.

3.3 Summary The NRC staff has reviewed the request by the licensee to revise the TS for Fermi 2. The proposed change is consistent with the STSs and TSTF-306, Revision 2, and provides reasonable assurance of overall plant safety. Based on the review, the NRC staff concludes that the proposed changes are acceptable.

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4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any eft'luents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (77 FR 20073, dated April 3, 2012). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Brian E. Lee Date of issuance: August 29, 2012

Mr. Jack M. Davis August 29,2012 Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166

SUBJECT:

FERMI 2 - ISSUANCE OF AMENDMENT FOR ADOPTION OF TSTF-306 (TAC NO. ME7720)

Dear Mr. Davis:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 189 to Facility Operating license No. NPF-43 for the Fermi 2 facility. The amendment consists of changes to the technical specifications (TSs) in response to your application dated December 20, 2011 (Agencywide Documents Access and Management System (ADAMS)

Access No. ML113550138).

The amendment revises TSs requirements related to primary containment isolation instrumentation. The changes are in accordance with NRC-approved Technical Specification Task Force (TSTF), Improved Standard Technical Specifications (ISTS) change TSTF-306, Revision 2.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA!

Mahesh L. Chawla, Project Manager Plant licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosures:

1. Amendment No.189 to

2. Safety Evaluation NPF-43 cc w/encls: Distribution via listServ DISTRIBUTION:

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NRRlLPL3-1/PM NAME IFrankl MChawla DATE 08/29/12 08/29/12 OFFICIAL RECORD COPY