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Amend 102 to Licenses NPF-72 & NPF-77,revising TS 3.9.3 Re Use of Gamma-Metrics post-accident Source Range Neutron Flux Monitors as Alternative to Westinghouse Source Range Neutron Flux Monitors During Mode 6 Operations (Refueling)
	ML20207F118
Person / Time
Site:	Byron, Braidwood
Issue date:	06/02/1999
From:	Anthony Mendiola; NRC (Affiliation Not Assigned)
To:	;
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ML20207E887	List: ML20207F118;
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	NUDOCS 9906080064
	Download: ML20207F118 (10)
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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. soseH001

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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-72 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated March 22,1999, 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 j

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-72 is hereby amended to read as follows:

9906090064 990602 PDR ADOCK 05000454 p

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2-(2)

Technical Soecifications The Technical Specifications contained in Appendix A as revised through'.

Amendment No.102 and the Environmental Protection Plan contained in

. Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the fac!!ity in accordance with the Technical

- Specifications and the Environmental Protection Plan.

l 3.

This license amendment is effective as of the date of its issuance and shall be

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implemented within 30 days.

FOR THE NUC R REGULATORY COMMISSION

/

'/

hony J. Mendiola, Chief, Section 2

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roject Directorate lli Division of Licensing Project Management l

Office of Nuclear Reactor Regulation 1

Attachment:

Changes to the Technical Specifications Date oflasuance: June 2,1999 t.

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. UNITED STATES

. g NUCLEAR REGULATORY COMMISSION -

o WASHINGTON, D.C. 300064001 6 **

COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No.102 j

License No. NPF-77 1.

The Nuclear Regulatory' Commission (the Commission) has found thati A.

The application for amendment by Commonwealth Edison Company (the licensee) dated March 22,1999, 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-77 is hereby amended to read as follows

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(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.102 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date if its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

'f An ony J. Mendiola, Chief, Section 2 oject Directorate ill Division of Licensing Project Managernent Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofissuance: June 2,1999 i

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ATTACHMENT TO LICENSE AMENDMENT NOS.102 AND 102 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 QQQKET NOS. STN 50-456 AND STN 50-457 I

Replace the following pages of the Appendix "A" Technical Specifications with the attached 1

pages. The revised pages are identified by amendment number and contain vertical lines

}

indicating the area of change.

Remove Pages insert Paoes l

i 3.9.3-1 3.9.3-1 B 3.9.3-1' B 3.9.3-1 B 3.9.3-2 B 3.9.3-2 B 3.9.3-3 8 3.9.3-3 8 3.9.3-4 8 3.9.3-4 l

l 1

F 1

Nuclear Instrumentat. ion l.

.' f 3.9.3 E

~ 3.9 REFUELING OPERATIONS e

l3.9.3 Nuclear Instrumentation LC0 -3.3.3L Two source range neutron flux monitors shall'be OPERABLE.

APPLICABILITY:

MODE 6..

l-ACTIONS CONDITION

. REQUIRED ACTION COMPLETION TIME-j A. _One~ required source A.1' Suspend CORE Immediately range neutron flux ALTERATIONS.

monitor inoperable.

E A.2

. Suspend positive Immediately reactivity additions.

B.. Two required source B.I.

Initiate action to Immediately range.. neutron flux restore one source.

monitors inoperable, range neutron flux monitor to OPERABLE status.

B.2:

Perform SR 3.9.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l-i

.'BRAIDWOOD)-UNITS.1&2 3.9.3 Amendment 102 & 102 l

p9 Nuclear Instrumentation

]

B 3.9.3

B 3.9 ~ REFUELING ~0PERATIONS' B 3.9.3 Nuclear, Instrumentation BASES BACKGROUND' The source range neutron flux monitors are used during refueling operations to monitor the core reactivity

. condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS). These detectors are located external to the reactor vessel'and -

detect' neutrons leaking from the core. The use of

)ortable detectors is permitted, provided the

.C0 requirements are met.-

The installed Westinghouse source range neutron flux l

monitors are boron trifluoride detectors operating in the proportional region of the gas filled detector characteristic curve. The detectors monitor the neutron flux in counts wr second. The instrument range covers six decades (1 to 1E+6 cps) (Ref.1). The installed source range Gamma-Metrics post accident neutron flux monitors are

' enriched U-235 fission chambers operating in the ion chamber region of the gas filled detector characteristic curve. The detectors monitor the neutron flux in counts per second.

The instrument range covers six decades (0.1 to 1E+5 cps).

The detectors also provide continuous visual indication in the control room to alert operators to a possible dilution accident. The NIS is designed in accordance with the criteria presented in Reference 2.

If used.

portable detectors must be functionally eouivalent to the installed NIS source range monitors. While multiple source range neutron flux monitors are available (i.e.. four installed monit. ors and the potential for the use of 1

portable detectors) only two source range neutron flux 1

monitors.are required to be OPERABLE.

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3RAIDWOOD - UNITS 1 & 2 B 3.9.3 - 1 Amendment 102 & 102 l

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Nuclear Instrumentation B 3.9.3 BASES

- APPLICABLE Two OPERABLE source range neutron flux monitors are recuired SAFETY ANALYSES to provide a signal to alert the operator. to unexpectec changes in core reactivity such as with a boron dilution i

accident (Ref. 3) or an.mproperly loaded fuel assembly.

The need for a safety analysis for an uncontrolled boron dilution accident is eliminated by isolating all.unborated water sources as required by LC0 3.9.2. "Unborated Water Source Isolation Valves."

The source ra'nge neutron flux monitors have no safety

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function in MODE any UFSAR design,6 and are not assumed to function during basis accident or transient. The source range neutron flux monitors provida the only on-scale monitoring of. the neutron flux level during refueling.

Therefore, they are being retained in the Technical Specifications.

LC0 This LC0 requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be OPERABLE. each monitor must provide visual indication.

APPLICABILITY In MODE 6. two source range neutron flux monitors must be-OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels.

In MODE 2 below the intermediate range neutron flux interlock setpoint (P-6), and in MODES 3. 4. and 5 with the R d Control System capable of rod withdrawal or with all rods not fully inserted the installed Westinghouse source range neutron flux monitors are' required to be OPERABLE by LCO 3.3.1. " Reactor Trip System (RTS) Instrumentation."

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BRAIDWOOD - UNITS 1 & 2 B 3.9.3 Amendment 102 & 102

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w Nuclear Instrumentat. ion B 3.9.3 BASES ACTIONS-A.1 and A.2

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With only one required source range neutron flux monitor l

03ERABLE. redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS ~and positive reactivity additions must be suspended immediately.

Performance of Required Action A.1 or A.2 shall not preclude completion of movement of a component to a safe position or normal

- heatup/cooldown of the coolant volume for the purpose of system temperature control.

B.1 and B.2 With no required scurce range neutron flux monitor OPERABLE, l

there are no direci means of detecting changes in core reactivity. There, ore, action to restore a monitor to DPERABLE status shall be initiated immediately and continued, until a source range neutron flux monitor is restored to OPERABLE status.

Since CORE ALTFRATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE.

This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

9

Nuclear Instrumentation B 3.9 3 BASES SURVEILLANCE' SR 3.9.3.1

' REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK which is a l

comparison of the parameter indicated on one channel to a-similar parameter on other channels.

It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loadtng' and core geometry can result in significant differences

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between source range channels but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LC0 3.3.3.

SR 3.9.3.2 SR 3.9.3.2 is the erformance of a CHANNEL CALIBRATION every 18 months. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.

The CHANNEL CALIBRATION for the source range neutron flux monitors consists of obtaining the detector discriminator curves, evaluating those curves, and comparing the curves to the manufacturer's-data. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that ap)1y during a plant outage. Operating experience has shown t1ese components usually pass the Surveillance when

. performed at the 18 month Frequency.

REFERENCES 1.

UFSAR. Table 7.5-2.

2.

10 CFR 50. Appendix A. GDC 13. GDC 26. G C 28. and GDC 29.

3.

.UFSAR. Section 15.4.6.

BRAIDWOOD - UNITS 1 & 2 B 3.9.3-4 Amendment 102 & 102

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ML20207F118

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