ML20247R853
| ML20247R853 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/31/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20247R858 | List: |
| References | |
| DPR-66-A-141, NPF-73-A-017 NUDOCS 8906080002 | |
| Download: ML20247R853 (13) | |
Text
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UNITED STATES p
M '.g NUCLEAR REGULATORY COMMISSION p
E WASHINGTON, D. C. 20555 s
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER YALLEY POWER STATION, UNIT NO. 1 AMENDMENT.TO FACILITY OPERATING LICENSE Amendment No. 141 License No. DPR-6C 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.-
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated ilanuary 5,1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission;
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C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the nealth and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; b.
D.
The issuance of this amendment will not be inimical to the comon I
defense and security or to the health and safety of the public; j
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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I 2.
Accordingly,'the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arrendment, and paragraph 2.C.(?) of Facility Operating License No. DpR-66 is hereby amended to read as follows:-
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.-141, are hereby incorporated'in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on issuance, to be implemented within'60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
. Stolz, Directo Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: fiay 31,- 1989 t
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' i ATTACHMENT TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE N0.-DPR-66 DOCKET fl0.L50-334 Replace the following pages of Appendix A (Technical Specifications) with.the enclosed pages as indicated. The revised pages are identified by aniendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 1-18 3/4 1-18
.3/4 1-19 3/4 1-19 3/4 1-20a 3/4 1-20a P3/4 1-4 B3/4 1-4 l
l
NEACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length shutdown and control rods shall be OPERABLE and l positioned within i 12 steps (indicated
- position, as determined in occordance with Specification 3.1.3.2) oftheirgroupstepcounterdemandl position.
APPLICABILITY:
MODES 1* and 2*
ACTION:
a.
With one or more full length rods inoperable due to being immovable as a
result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod misaligned from its group step counter demand position by more than i 12 steps (indicated position determined in accordance with Specification 3.1.3.2), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one full length rod trippable but inoperable due to causes other than addressed by ACTION a above, or misaligned from its group step counter demand position by more than i 12 steps (indicated position determined in accordance with Specification 3.1.3.2),
POWER OPERATION may continue provided that within one hout either:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The rod is declared inoperable and the remainder of the rods in the. group with the inoperable rod are aligned to within 1 12 steps of the inoperable rod while maintaining the rod I
^
sequence and insertion limits of Figures 3.1-1 and 3.1-2.
The THERMAL POWER level shall be restricted pursuant to l
Specification 3.1.3.6 during subsequent operation, or 3.
The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
The THERMAL POWER level is reduced to less than or equal to' 75%
of RATED THERMAL POWER within the hour and, within the next 4
hours the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.
BEAVER VALLEY - UNIT 1 3/4 1-18 Amendment No. iL 141 0
LIMITING CONDITION ~ FOR OPERATION (Continued) b)
The SHUTDOWN. MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c)
A _ power distribution map is obtained from the movable N
incere detectors and FQ(Z) and FA H are-verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
d)
A reevaluation of each accident analysis of Table 3.1-1 is performed within 5
days; this reevaluation shall confirm _ that the previously analyzed results of these accidents remain valid for the duration' of operation under these conditions.
d.
With more than one rod trippable but inoperable due to causes other than addressed by Action a
- above, POWER OPERATION may continue provided that:
1.
Within one
- hour, the remainder of the rods in the bank (s) with the inoperable rods are aligned to within i 12 steps of the inoperable rods while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2.
The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.
Thc_ inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 Each shutdown and control rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.
4.1.3.1.2 The position of each full length rod shall be determined to be l within i 12 steps of the associated group demand counter by verifying the individual rod position at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during intervals when the Rod Position Deviation monitor is inoperable, then verify the group position at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
"See Special Test Exception 3.10.2 and 3.10.4 l
1 BEAVER VALLEY - UNIT 1 3/4 1-19 Miendment No. Iq,141 l
$IMIT'ING CONDITION FOR OPERATION (Continued)
-APPLICABILITY:
MODES l'and 2#
ACTION:
a.
If the Rod Position Indicating System indicates (2) a potentially misaligned rod (s), this indication shall be verified immediately (within 15 minutes) by measuring the analog rod position channel primary voltage.
If this measurement confirms that a rod is misaligned, Specification 3.1.3.1 is applicable.
l b.
With a
maximum of one group demand position indicator per bank inoperable, either:
1.
. Verify that all. rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps-(indicated position) of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
c.
With a
maximum of one analog rod position indicator per bank inoperable, (following a
one-hour thermal soak at less than 50%
of Rated Thermal Power or at anytime when Rated Thermal Power is greater than or equal to 50%) either, 1.
Determine rod position for the affected rod (s) by measuring the detector primary voltage, as follows:
a.
Immediately b.
If the associated rod moved greater than 6 steps (greater than 12 steps if all the rods in the group have been determined to be within 6 steps of group demand counter indicator by primary voltage measurements within the previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Y c.
At 4
hour intervals if the affected rod (s) are not fully inserted or withdrawn.
d.
At 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> intervals if the affected rod (s) are fully inserted or withdrawn, or i
BEAVER VALLEY - UNIT 1 3/4 1-20a Amendment No. M,141 m____________________._______.__
O
. REACTIVITY CONTROL SYSTEMS BASES position indicators (after thermal soak after rod motion) is sufficient verification that the control rods are above the insertion limits below 50 percent. power.
Above 50 percent power, reliance is placed on the
- analog rod position indicator channels to assure that control rods are above the insertion limits.
.The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.
Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER.
These restrictions provide assurance of fuel rod integrity during continued operation.
.In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.
Continuous monitoring of rod position with respect to insertion limits and rod deviation is provided by the rod insertion limit monitor and rod deviation' monitor, respectively.
OPERABILITY of the -rod deviation monitor is verified by a functional test at least once per 7 days and by comparison _of the indicated analog positions versus the respective group demand counters at least once per.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the rod deviation monitor or the rod insertion limit monitor is INOPERABLE, the frequency of manual comparison of indicated rod position is increased to an interval of at least once per 4-hours.
For Specification 3.1.2.1 ACTION c. and d., it is incumbent upon the plant to verify the trippability of the inoperable control rod (s).
Trippability is defined in Attachment C
to a
letter dated December 21, 1984, from E. P. Rahe (Westinghouse) to C. O. Thomas (NRC).
This may be by verification of a
control system failure, usually electrical in
-nature, or that the failure is associated with the control rod stepping mechanism.
In the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under the requirements of ACTION a.
BEAVER VALLEY - UNIT 1 B 3/4 1-4
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AmendmentNo.lq,141
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UNITED STATES
! ; [. s, [j NUCLEAR REGULATORY COMMISSION
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.E W ASHINGTON, D. C. 20555 j
DUQUESNE LIGHT COMPANY
.0HIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 17 License No. NPF-73 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee)~ dated January 5,1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 6
E.
The issuance of this amendment is in accordance with 10 CFP. Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
4
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_-_-______m____
o
l' 2.
Accordingly, the license is~ amended by changes to the Technical Specificaticos as indicated in the attachment to this license amenon.ent, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 17, and the Environmental Protection Plan contained in Appendix P2, both of which are attached hereto, are hereby incorporated in the license. DLCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective on issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
Jo
. Stolz, Director Project Directorate I-4 Division of Peactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 31,1989
o ATTACHFENT TO LICENSE AMENDitENT N0; 17 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A (Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
1
' Remove Insert 3/4 1-18 3/4 1-18 3/4 1-19 3/4 1-19 B3/4 1-4 B3/4 1-4 l
4 l
l
i REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length shutdown and control rods shall be OPERABLE and I
positioned within 12 steps (indicated position, as determined in accordance with Specification 3,1.3.2) of their group step counter demand position.
l APPLICABILITY:
MODES 1* and 2*
pr' ION:
a.
With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTOOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod misaligned from its group step counter demand position by more than 12 steps (indicated position determined in accordance with Specification 3.1.3.2), be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one full length rod trippable but inoperable due to causes other than addressed by ACTION a above, or misaligned from its group step counter demand position by more than 12 steps (indicated position determined in accordance with Specification 3.1.3.2), POWER OPERATION may continue provided that within one hour either:
1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable rod while maintaining the rod sequence and in-sertion limits of Figure 3.1-1.
The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.
The rod is declared inoperable and the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the hour and, within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85% of RA1ED THERMAL POWER.
- See Special Test Exceptions 3.10.2 and 3.10.3 BEAVER VALLEY - UNIT 2 3/4 1-18 Amendment No. 17 i
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REACTIVITY CONTROL SYSTEMS
- LIMITING ~ CONDITION FOR OPERATION'(Continued) b)
- The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined-at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
?
c)
A power distribution map'is obtained from the movable incore detectors and F (Z) and F are verified to'be 9
H within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> d)
A reevaluation of each accident analysis of Table 3.1-1.is
. performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.
d.
With more than one rod trippable but inoperable due to causes other than addressed by Action a above, POWER OPERATION may continue provided that:
1.
Within one hour, the remainder of the rods in the bank (s) with the inoperable rods are aligned to within t12 steps of the inoperable rods while maintaining the rod sequence and insertion' limits of Figure 3.1-1.
The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.
The--inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 Each shutdown and control rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least'10 steps in any one direction at least once per 31 days.
4.1.3.1.2 The position of each full length rod shall be determined to be within l
1 12 steps of the associated group demand counter by verifying the individual rod position at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during intervals when the Rod
. Position Deviation monitor is inoperable, then verify the group position at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
BEAVER VALLEY - UNIT 2 3/4 1-]J Amendment No. 17
f-9
_RFACTIVITY CONTROL SYSTEMS BASES l
3/4.1.2 B0 RATION SYSTEMS (Continued)
The boration capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 1% ak/k after xenon decay and cooldown from 200 F to 140 F.
-This condition requires either 2315 gallons of 7000 ppm borated water from the boric' acid storage tanks or 10,196 gallons of 2000 ppm borated water from the refueling water storage tank.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that 1) acceptable power distri-bution limits are maintained, 2) the minimum SHUTDOWN MARGIN is maintained, and
- 3) the potential effects of rod misalignment on associated accident analyses are limited.
OPERABILIT.Y of the movable control assemblies is established by observing' rod motion and determining that rods are positioned within 12 steps (indicated position), of the respective group demand counter position.
The OPERABILITY of the control rod position indication system is required to deter-mine control rod positions and thereby ensure compliance with the control rod alignment'and insertion limits.
The ACTION statements which permit limited variations from the basic re-quirements are accompanied by additional restrictions which ensure that the original design criteria are met.
Misalignment of a rod requires measurement of peaking f actors and a restriction in THERMAL POWER.
These restrictions pro-vide assurance of fuel rod integrity during continued operation.
In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.
Continuous monitoring of rod position with respect to insertion limits and rod deviation'is provided by the rod insertion limit monitor and rod deviation monitor, respectively.
If the rod deviation monitor or the rod insertion limit monitor is inoperable, the frequency of manual comparison of indicated rod posi-tion is increased to an interval of at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses.
Measurement with T greater than or equal avg to 541 F and with all reactor coolant pumps operating ensures that the 4
measured drop times will be representative of insertion times experienced dur-I ing a reactor trip at operating conditions.
]
For Specification 3.1.3.1 ACTIONS c. and d., it is incumbent upon the plant to verify the trippability of the inoperable control rod (s).
i Trippability is defined in Attachment C to a letter dated December 21, 1984, from E. P. Rahe (Westinghouse) to C. O. Thomas (NRC).
This may be by verification of a control system failure, usually electrical in nature, or that_the failure is associated with the control rod stepping mechanism.
In i
the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under the requirements of ACTION a.
BEAVER VALLEY - UNIT 2 B 3/4 1-4 Amendment No. 17