ML20207E884
| ML20207E884 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/02/1999 |
| From: | Anthony Mendiola Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207E887 | List: |
| References | |
| NPF-37-A-109, NPF-66-A-109 NUDOCS 9906070192 | |
| Download: ML20207E884 (8) | |
Text
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1 UNITED STATES g
j NUCLEAR REGULATORY COMMIS810N r
WASWNOToN, D.C. 30006 40M l
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-454 BYRON STATION. UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. NPF-37 t
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 Act, and the rules and regulations of the Commission; l
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 j
i E.'
The issuance of this amendmentis 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-37 is hereby amended to read as follows:
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9906070192 990602 PDR ADOCK 05000454 P
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2-(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.109 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 facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be
' implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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A hony J. Mendiola, Chief, Section 2 roject Directorate lli Div!sion of Licensing Project Management Office of Nuclear Reactor Regulation Attschment:
Changes to the Technical-Specifications Date ofissuance: June 2,1999 4
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1 esqk UNITED STATES -
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NUCLEAR REGULATORY COMMISSION '
WASHINGTON, D.C. 30006 4001 1>,.....
I COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2' AMENDMENT TO FACILITY OPERATING LICENSE q
Amendment No.109 License No. NPF-66 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 Act, and the rules and regulations of the Commission; s
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 satisfe' d.
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-66 is hereby amended to read as follows:
s
- (2)..
Technical Soecifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No.109 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which
- were attached to License No. NPF-37, dated February 14,1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is 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 of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/L W An y J. Mendiola, Chief, Section 2 oject Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: June 2,1999 l
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f ATTACHMENT TO LICENSE AMENDMENT NOS.109 AND 109 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66
' DOCKET NOS. STN 50-454 AND STN 50-455
. Revise the Appendix A Technical Specifications by removing the pages identified below and l
. inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Bemove Paaes insert Paaes 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 B 3.9.3 4 B 3.9.3 4 l
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1p Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 " Nuclear Instrumentation.-
LCO 3.9.3-Two. source range neutron flux monitors shall be OPERABLE.
APPLICABILITi:
MODE 6.
ACTIONS-CONDITION REQUIRED ACTION.
COMPLETION TIME
( A. ?0ne required source -
A.1 Sussend CORE Immediately I
range neutron flux ALT ERATIONS.
monitor' inoperable.
M A.2 Suspend positive Immediately' reactivity additions.
~ B. Two. required source B.1 Initiate action to Immediately_
l range neutron flux restore one source monitors inoperable.
range neutron flux monitor to OPERABLE status.
E-B.2
. Perform SR 3.9.1.1.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1
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A BYRONJ-10 NITS 1 & 2
- 3. 9.3 - 1 Amendment 109 & 109
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L Nuclear Instrumentat. ion 1
B 3.9.3 B 3.9 REFUELING OPERATIONS-B 3.9.3 Nuclear Instrumentation BASES
, BACKGROUND The source range neutron flux monitors are used during refueling o condition. perations to monitor the core reactivity 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 yortable detectors is permitted, provided the
_C0 requirements are met.
The installed Westinghouse sour:e range neutron flux-l monitors are boron trifluoride detectors operating in the prooortional region of the gas filled detector cha'racteristic curve. The detectors monitor the neutron flux in counts per 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 equivalent to the installed NIS source range monitors.
While multiple source range neutron _ flux monitors are available (i.a.. four installed monitors and the potential for the use of portable detectors). only two source range neutron flux monitors are required to be OPERABLE.
BYRON - UNITS 1 & 2 B 3.9.3 - 1 Amendment 109 & 109 3
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Nuclear Instrumentat. ion l
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B 3.9'.3 l
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BASES l
APPLICABLE Two OPERABLE source range neutron flux monitors are required SAFETY ANALYSES to provide a signal to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 3) or an improperly loaded fuel assembly.
. The need for a safety analysis for an uncontrolled boron t
dilution accident is eliminated by isolating all unborated water sources as required by LCO 3.9.2. "Unborated Water Source Isolation Valves."
.The source range neutron flux monitors have no safety _
function in MODE 6 and are not assumed to function during any UFSAR design basis accident or transient. The source range neutron flux monitors provide 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 l
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 Rod Control System capable of rod withdrawal or with all
. rods not fully inserted the installed Westinghouse source l
range neutron flux monitors are required to be OPERABLE by LC0 3.3.1 " Reactor Trip System (RTS) Instrumentation.
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l BYRON - ONITS 1 & 2 B 3.9.3 - 2 Amendment 109 & 109 l
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p Nuclear instrumentation 8 3.9.3 BASES.
r ACTIONS A.1'and A.2 With only one required source range neutron flux monitor OPERABLE. redundancy has been lost.
Since these instruments l
are the only direct means of monitoring core. reactivity 1
conditions. CORE ALTERATIONS and positive reactivity
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additions must be suspended immediately. Performance of Required Action A.1 or A.2 shall not preclude completion of movement of a. comp,onent to a safe position or normal heatup/cooldown or the coolant volume for the purpose of l
system temperature control.
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B.1 and B.2
.With no required source range neutron flux monitor OPERABLE.
l there are no direct means of detecting changes in core reactivity. Therefore, action to restore a monitor to OPERABLE status shall be initiated immediately and continued until a source range neutron flux monitor is restored to OPERABLE status.
Since CORE ALTERATIONS 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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. hour Frequency is reasonable, considering the low probability of a change in i
core reactivity during this time period.
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BYRON - UNITS 1 & 2 B 3.9.3 - 3 Amendment 109 & 109 4
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Nuclear Instrumentation B 3.9.3 l
BASES SURVEILLANCE SR 3.9.3.1 1
REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a 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 loading and core geometry can result in significant differences between source range channels. but each channel should be consistent with its local conditions.
The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.
SR 3.9.3.2 SR 3.9.3.2 is the aerformance 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 apaly 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 501. Appendix A. GDC 13. GDC 26. GDC 28 and GDC 29.
3.
UFSAR. Section 15.4.6.
BYRON --UNITS 1 & 2 B 3.9.3 - 4
' Amendment 109 & 109
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