ML19274F071
| ML19274F071 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/01/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19274F072 | List: |
| References | |
| TAC-13126, TAC-13127, NUDOCS 7906130061 | |
| Download: ML19274F071 (9) | |
Text
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_s UNITED STATES y
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NUCLEAR REGULATORY COMMisslON f, hf WASHINGTON, D. C. 20555 u e,/
ss, NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.36 License No. DPR-42 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated April 26, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules anc 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 regulations; D.
The issuance of this amendment will not be inimical to the cocmon 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 License No. DPR-42 is hereby amended to read as follows:
790613006/
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"(2)
Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment Nc. 36, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
.nis license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.hyuMdG A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:i EAY.
I 1979 O
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S UNITED STATES
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WASHINGTON, D. C. 20355 i
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 2
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AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated April 26, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), anu 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 (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 Comissich's regulations; D.
The issuance of this amendment will net be inimical to the corra, defense and security or to the health and safety of e
l the public; and i
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 satisifed.
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 License No. OPR-60 is hereby amended to read as follows:
.~
! "(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment flo. 30, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N ev:4de A. Schwencer, Chief Operating Reactors Branch il Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Cate of Issuance:
ray 7379 O
ATTACHMENT TO LICENSE AMENDMENT NOS. ?A AND gn FACILITY OPERATING LICENSE N05. DPR-42 AND DPR-60 DOCKET N05. 50-282 AND 50-306 Replace the following pages of the Technical Specifications contained in Appendix A of the above-indicated licenses with the attached pages bearing the same numbers, except as otherwise indicated.
The changed areas on the revised pages are reflected by a marginal line.
Remove Insert TS. 3.5-2 TS 3.5-2 TS. 3.5-3 TS 3.5-3 Table TS. 3.5-1 Table TS 3.5-1 Table TS. 3.5-3 Table TS 3.5-3 O
TABLE TS.3.5-3 II INSTRUMENT OPERATING CONDITIO!1S FOR EMERGENCY COOLING SYSTEM i
2 3
4 MINIMUM MINIMUM PERMISSIBLC OPERATOR ACTION IF OPERABLE DECREE OF BYPASS CONDITIONS OF COLUMN FUNCTIONAL UNIT CllANNELS REDUNDANCY CONDITIONS 1 or 2 CANNOT BE HET 1.
SAFF.TY INJECTION a.
finiua l 2
1 Ilot shutdown ***
b.
liigh Containment Pressure 2
1 liet shutdown ***
c.
Ste'm Generator Low Steam 2
1 primary pressure llot shutdown ***
Pressure / Loop less than 2000 psig
- d. + Pressurizer Low Pressure 1*
2 primary pressure llot shutdown ***
and Low Level less than 2000 psig e.
Pressurizer Low Pressure 2
1 primary pressure llo t shutdown ***
1ess th.in 2000 psig 2.
2 llot shutdown ***
3 a.
Manual S
Ilot shutdown ***
3 h.
111 -11 1 Containment Pres-nure (Contalument Spray) f, E
Channel a 2
1 T
Channel b 2
1 Channel c 2
1 m
'R Logic 2
1
.a
- Each channel has one pressurizer pressure and one pressurizer level signal.
- Must actuate 2 switches simultaneously.
. *** - If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken to place the unit in cold shutdown condition.
- Functional Unit 1.d requirements are no longer applicable for a particular Prairie Island unit following replacement of the coincident low pressurizer level and pressure SI by the pressurizer low pressure
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TABLE TS.3.5-1 ENGINEERED SAFETY FEATURES INITIATION ItiSTRUffEllT LIllITI!IC SET POItiTS
.l FUtiCTIONAI, UllIT CilAtitlEL 1.Ill1 tit 1C SET POI!1TS*
1 liigh Containment Pressure ( 11 1 )
Safety Injection
- 14 psig 2
Iligh Contafnment Pressure (111 -111 )
- a. Containment Spray 123 psig
- b. Steam Line Isolation 117 psig of Both Lines 3+
Pressurizer Low Pressure and Low Level Safety Injection *
>l815 psig 15 per cent (of dis-tance) between the instrument taps 3.a Pressurizer Low Pressure Safety Injection *
>l815 psig 4
Low Steam Line Pressure Safety Injection
- __500 psig Lead Time Constant
>12 seconds Lag Time Constant 12 seconds 5
liigh Steam Flow in a Steam Line Steam Line Isolation d/pcorrespp'ndingto Coincident willi Safety Injection of Affected Line 10.745 x 10 lb/hr and 1.ow T at 1005 psig g
avg
>540 F ft 6
liigh-hlgh Steam. Flow in a Steam Line Isolation id/pcorrespgnding g:
Steam 1.tne Colucident with of Affected I.ine to 4.5 x 10 lb/hr Safety injection at 735 psig vi 7
liigh Prennure Difference Between Containment Vacuum 10.5 psi g
]
Shield Building and Containment Breakers o
8 liigh Temperature in Ventilation Ducts Ventilation System 1120 F Isolation Dampers
.
- Initiates also containment isolation, feedwater line isolation and starting of all containment fans.
.d{pmeansdifferentialpressure e
Functional Unit 3 requirements are no longer applicable for a particular Prairie Island unit following replacement of the coincident low pressurizer level and pressure SI by the pressurizer low pressure sr wrn,einn I no I.- afrer which time Functlonal Unit 3.a renntrementa become effeetive.
TS.3 5-2 Safety Injection The Safety Injection System is actuated auto =atically to provide emargency cooling and reduction of reactivity in the event of a less-ef-coolant accident or a steam line break accident.
Safety injection in response to a less-of-coolant accident (LOCA) is providad by a high contain=ent pressure signal backed up by the low pressurizer pressure signal".
These conditions vould accompany the depressurization and coolant loss during a LOCA.
Safety injection in response to a steam line break is provided directly by a low steam line pressure signal, backed up by the low pressurizer pressure signal and, in case of a break within the contain=ent, by the high containment pressure signal.
The safety injection of highly borated watet will-of f set the te=perature-induced reactivity addition that could otherwise result fro: cooldown following a steam line break.
Centainment Spray Containment sprays are also actuated by a high contain=ent pressure signal (Hi-Hi) to reduce containrent pressure in the event of a loss of coolant or steam line break accident inside the contain=ent.
The containment sprays are actuated at a higher containment pressure (approximately 50% of design containment pressure) than is saf ety injection (10% of design).
Since spurious actuation of contain=ent spray is to be avoided, it is initiated on coincidence of high contain=ent pressure sensed by three sets of one-out-of-two containment pressure signals provided for its actuation.
Containment Isolation A containment isolation signal is initiated by any signal causing automatic initiation of saf ety injection or may be initiated =anually.
The containment isolation system provides the means of isolating the various pipes passing through the containment walls as required to prevent the release of radioactivity to the environ =ent in the event of a loss-of-coolant accident.
+The pressurizer low pressure SI initiation logic will be installed to replace the coincident low pressurizer level and pressure SI actuation logic at the earliest scheduled refueling.
Amendment Mos. 36/30
ZZ TS.3.5-3 Stea: Line Isolation In the event of a stea: line break, the stea: line stop valve of the affected line is auto atically isolated to prevent continuous, uncontrolled stea= release from more than one steam generator.
The stea= lines are isolated on high containcent pressure (Hi-Hi) or high steam line flow in coincidence with low T and safety injection or high steam flow (Hi-Hi) in coincidence"w!th saf ety injection.
Adequate protection is afforded for breaks inside or outside the containment even when it is assumed that the steam line check valves do not function properly.
Ventilation Svstem Isolation In the event of a high energy line rupture outside of contain=ent, isolation da:pers in certain ventilation ducts are closed. g redundant Li=iting Instrument Setpoints 1.
The high containment pressure limit is set at about 10% of the
=ax1=um internal pressure.
InitgionofSafetyInject{og protects against loss of coolant or steac line break accidents as discussed in the saf ety analysis -
2.
The Hi-Hi containcent pressure limit is set at about 50% of the maximum internal pressure for initiation of contain=ent spray and at about 30% for initiation of steam line isolation.
Initiation of Containment Spray and St g Line Isolation protects againstgrge loss of coolant or steam line break accidents as discussed in the saf ety analysis.
3.
The pressurizer low pressure limit is set subs tantially below system operating pressure limits.
However, it is sufficiently high to protect againstgloss of coolant accident as shown in the safety analysis.
4.
The steam line low pressure signal is lead / lag co=pensated and its setpoint is set well above the pressure expected in the event of a large as shown in t'e safetyanalysis.geamlinebreakaccident 5.
The high steam line flow limit is set at approx 1=ately 20% of nominal full-load flow at the no-load pressure and the high-high steam line flow limit is set at approxi=ately 120% of nominal full-load flow at the full load pressure in order to protect against large steam break accidents.
The coincident low T setting limit for stea: line isolation initiation is se!"$elow its hot shutdote value.
The saf ety analysis shows that these se iggsprovideprotectien in the event of a large steam break Amendment Nos. 36/30