ML20008F025
| ML20008F025 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/03/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008F026 | List: |
| References | |
| NUDOCS 8103120068 | |
| Download: ML20008F025 (11) | |
Text
a uoq S
UNITED STATES E
h NUCLEAR REGULATORY COMMISSION e
wAsamcTos. o. c. 20sss s,7.c-/)j DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated May 14, 1980, 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 Connission'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 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.
120003 s10i
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachtent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as folicws:
(2) Technical Scecifications The Technical Specificatiens contained in Appendices A and 3, as revised thrcush Amendment No. 40, are hereby incorpcrated in the license. The licensee shall operate the facility in acccrdance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
kVarga a
, Operating Reacters. a ch fl Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3, 1981 4
s
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. OPR-66 DOCKET NO. 50-334 i
Revise Appendix A as follows:
Remove Pages Insert Pages XVII XVII 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/ 4 3-21 3/4 3-21 3/4 3-24 3/4 3-24 3/4 3-27 3/4 3-27 3/4 3-31 3/4 3-31 3/4 7-32b
. 3/4 7-32b W
f 4
a
ADMINISTRATIVE CONTROLS PAGE SECTION Consultants.................................................
6-8 6-8 Meeting Frequency...........................................
6-9 Quorum......................................................
Review......................................................
6-9 Audits...................................
6-10 6-10 A u t h o r i ty...................................................
Records.....................................................
6-10 6.6 REPORTABLE OCCURRENCE ACTI0N................................
6-11 6.7 SAFETY LIMIT VI0LATION......................................
6-12 6-12 6.8 PROCEDURES..................................................
6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE AND REPORTABLE OCCURRENCES........................
6-12 6-13 Startup Report..............................................
6-13 An n u al Re p o rt s..............................................
6-14 Monthly Operating Report....................................
5-14 Reportable Occurrences......................................
6-14 Prompt Notification with Written Followup...................
6-16 Thi rty Day W ritten Reports..................................
6-17 6.9.2 SPECIAL REP 0RTS...........................................
6-17 6.10 RECORD RETENTION...........................................
6-19 6.11 RADIATION PROTECTION PR0 GRAM...............................
6-19 6.12 HIGH RADIATION AREA........................................
6.13 ' ENVIRONMENTAL QUALI FI CATION................................
6-19 i 4
BEAVER VALLEY - UNIT 1 XVII Amendment No. 3240 4
(D9 rii
- u I Alli i
- 3. t 't (Cont inued) g ENGINEERED SAll.lY_11 Altliti. AcillAlloff SYS1EM INSIRUMENI ATION C
MINIMUM
$1 TOTAL NO.
CilANNELS CllANNELS APPLICABLE
=
FUNCTIONAL UNIT OF CilANNELS - TO TRIP OPERABLE MODES ACTION 5.
FEEDWATER ISOLAlION a.
Steam Generator 3/ loop 2/ loop in 2/ loop in' 1, 2, 3 14 Water Level--
any oper-each oper-liigh-liigh ating loop ating loop 6.
LOSS OF POWER dd a.
4.16kv Bus 1/4.16kv Bus 1/4.16kv Bus 1/4ky Bus 1, 2, 3, 4 33
- 1. Loss of Voltage l',
(trip feeder) 1/4.16kv Bus 1/4kv Bus 1, 2, 3, 4
- 2. Loss of Voltage e
(start diesel) 1/4.16kv Bus b.
Grid Degraded Voltage 2/4.16ki Bus 2/ Bus 2/ Bus 1, 2, 3, 4 34 (4.16kv Bus) c.
Grid Degraded Voltage 2/41tuv llux 2/Ilus 2/llus 1, 2, 3, 4 34 (480v Bus) 2g a
3n f
TABLE 3.1-3 (Concinued) 7ABLE NOTATION
- rip function may be bypassed in this MODE below P-ll.
T
- The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.
~
ACTION STATEMENTS ACTION 13 - With.the number of OPERABLE Channels one less than the Total Number of Channels, 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to I hour for surveillance testing per Specification 4.3.2.1.1.
ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels:
- a. Below P-11 or P-12, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding P-11 or F-12; otherwise be in a-least HOT STANDBY within the following 6 nours.
- b. Abcve P-li and P-12, place the inoperable channel in the tripped condition within i hour; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.
ACTION 15 - With a channel associated wi-h ar. cpera*'ng loop inoperable, restore the inoperable channel to GPERALLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel associated with an operating loop may be bypassed for'up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
l l
ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels:
- a. Below P-ll or P-12, place the inoperable channel in the bypass condition; restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding P-ll or P-12; otherwise be in at least HOT SHUTOOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
BEAVER VALLEY - UNIT 1 3/4 3-20 Amendment No. 40 9
TABLE 3.3-3 (Centinued)
- b. Above P-il or P-12, demonstrate that the Minimum Channels OPERASLE requirement is met within 1 heur; operation may continue with the inoperable channel bypassed and a
additional channel may be oypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> tcr surveillance testing per Specification 4.3.2.1.
ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are caintained closed.
ACTION 18 - With.the number of OPERASLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STAND 5Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN.within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 33 - With the number of OPERABLE Charinels one less than the Total Number of Channels, the Emergency Diesel Generator associated with the 4kv Bus shall be declared inoperable and the ACTION Statements for Specifications ~2.8.1.1 or 3.8.1.2, as appropriate shall apply.
ACTION 34 - With the number of OPERABLE Cnannels on less than the Total Number of Channels, STARTUP an-/or POWER OPERATION mL proceed until the performance of the rext recuired Channel Functional Test ;rovided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
EN3INEERED SAFETY FEATURES INTER'_0:K5 DESIGNATION CONDITION AND SETPOINT FUNCTION P-11 With 2 of _3 pressurizer P-il prevents or defeats pressure channels > 2010 the manual block of safety psig.
injection actuation on low oressurizer pressure coin-cident with low pressurizer ater level and on low steam line pressure.
Block steam line isolation on high pressure rate.
P-12 With 2 of 3 T channels Affects steam dump blocks.
< Sc p.
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3/4 3-21 Amendment No. 40 BEAVER VALLEY - UNIT 1
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1 TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 4.
Steam Line Pressure-Low a.
Safety Injection (ECCS) i 13.0#/23.0##
b.
Reactor Trip (from SI)
$ 3.0 c.
Feedwater Isolation 1 75.0(1) d.
Containment Isolation-Phase "A" 5 22.0#/33.0##
e.
Auxiliary Feedwater Pumps Not Applicable f.
Rx Plant River Water System 1 77.0#/110.0##
g.
Steam Line Isolation 58.0 5.
Containment Pressure--High-High a.
Containment Quench Spray 1 77.0 b.
Containment Isolation-Phase "B" Not Applicable c.
Control Room Ventilation Isolation 5 22.0#/77.0##
6.
Steam Generator Water Level--High-High a.
Turbine Trip-Reactor Trip i 2.5 b.
Feedwater Isolation i 78.0(1) 7.
Containment Presssure--Intermediate High-Hign a.
Steam Line Isolation d'8.0 8.
Steamline Pressure Rate--High Negative a.
Steamline Isolation 5 8.0 9.
Loss of Power a.
4.16kv Emergency Bus Undervoltage i 1.3 (Loss of Voltage)
'b.
4.16kv and 480v Emergency Bus Under-5 95 voltage (Degraded Voltage)
BEAVER VALLEY - UNIT 1 3/4 3-27 Amendment No. 40
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.3/4 3-31 A:endment No. 40
k TABLE 3.7-4 (Continued) rn 52 h
SAFETY RELATED llYDRAULIC SNUBBERS
ON, LOCATION AND ELEVATION IllACCESSIBLE
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RC-IISS-119 RC Reac. Cnt. Bldg.
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