ML20248J819
| ML20248J819 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/03/1989 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248J822 | List: |
| References | |
| NUDOCS 8904170090 | |
| Download: ML20248J819 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20556 E
l NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 87 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found.that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 18, 1988 as supplemented by letters dated September. 15, 1988 and March 10, 1989, 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 Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. OPR-42 is hereby amended to read as follows:
l l-l 8904170090 890403 PIIR ADOCK 05000282 P
j.. - '
)
. Technical Specifications j
The Technical Specifications contained in Appendix A, as revised through Amendment No. 87, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
1 4
3.
This license amendment is effective as of the date of its issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION "2
Theodore R. Quay, Act'ing Director Project Directorate 111-1 I
Division of Reactor Projects - III, IV, V i
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 3,1989 l
1
~
+
t ATTACHMENT T0 LICENSE AMENDMENTS NOS. 87 AND 80 FACILITY OPERATING LICENSES NOS. DPR-42 AND DPR-60
- 00CKETS NOS. 50-282 AND 50-306 i
l Revise Appendix A' Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines. indicating the area of change.
REMOVE INSERT
' TS.2.3-3 TS.2.3-3 TS.2.3-6 TS.2.3-6
. Table TS.3.5-2 (Page 2 of 2)
Table TS.3.5-2 (Page 2 of 2)
Table TS.4.1-1 (Page 2 of 5)
Table TS.4.1-1 (Page 2 of 5) n__.m_.___w-_m-m_.2_-_.___-___m___._____a.___._
________________a_
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TS.2.3-3 K6- 0.002 for T > T',
O for T < T' T3-10, see f(AI) as defined in d. above,
- f. Low reactor coolant flow per loop - >90% of normal indicated loop flow as measured at loop elbow tap.
- g. Open reactor coolant pump motor breaker.
(1)
Reactor coolant pump bus undervoltage -
275% of normal voltage.
(2)
Reactor coolant pump bus underfrequency -
f 258.2HZ h.' Power range neutron flux rate.
(1) Positive rate - $15% of rated power with a time constant >2 seconds (2) Negative rate - $15% of rated power with a time constant >2 seconds 3.
Ocher reactor trips-
- a. High pressurizer water level - $90% of narrow range instrument span.
- b. Low-low steam generator water level - 25% of narrow range instrument span.
- c. Low steam generator water level - >15% of narrow rangeinstrumentincoinegdencewithsteam/feedwater mismatch flow - $1.0 x 10 lbs/hr.
- d. Turbine Generator trip (1) Turbine stop valve indicators - closed (2) Low auto stop oil pressure - 245 psig l
- e. Safety injection - See Specification 3.5 B.
Protective instrumentation settings for reactor trip interlocks shall be as follows:
1.
"At Power" reactor trips that are blocked at low power (low-pressurizer pressure, high pressurizer level, and loss of flow for one or two loops) shall be unblocked whenever:
- a. Power range neutron flux is 212% of rated power or,
- b. Turbine load is 210% of full load turbine impulse pressure.
- The low steam generator water level in coincidence with steam /feedwater mismatch trip may be deleted following installation of the digital feedwater control system incorporating the median signal selector function. An acceptable verification and validation program shall be demonstrated to the satisfaction of the NRC Staff.
Prairie Island Unit 1 - Amendment No. 28,87 Prairie Island Unit 2 - Amendment No. 22,80 m
TS.2.3-6 The'other reactor trips specified in A.3. above provide additional protection.
l The safety injection signal trips the reactor to decrease the severity of the accident condition. The reactor is tripped when the turbine generator trips above a power level equivalent to the load rejection capacity of the steam-dump l'
valves. This reduces the severity of the loss-of-load transient.
The positive power range rate trip provides protection against rapid flux increases which are characteristic of rod ejection events from any power level. Specifically,.this trip compliments the power range nuclear flux high and low trip to assure that the criteria are met for rod ejection from l
partial power.'
\\
The negative power range rate trip provides protection satisfying all IEEE criter.ia to assure that minimum DNBR is maintained'above 1.30 for Exxon Nuclear-fuel and above 1.17 for Westinghouse fuel for all multiple control rod drop.
accidents. Analysis indicates (Section 14.1.3) that in th,e case of a single rod drop, a return to full power will be initiated by the automatic reactor' control system in response to a continued full power turbine load demand and it will not result in a DNBR of less than 1.30 for Exxon Nuclear fuel or 1.17 for Westinghouse fuel. Thus, automatic protection for a single rod drop is not required. Admini-strative limits in Specification 3.10 require a power reduction if design power distribution limits are exceeded by a single misaligned or dropped rod.
References:
(1) FSAR 14.1.1 (2) FSAR Page 14-3 (3) FSAR 14.2.6 (4) FSAR 14.3.1 (5) FSAR 14.1.2 4
(6) FSAR 7.2, 7.3 (7) FSAR 3.2.1 (8) FSAR 14.1.9 (9) FSAR 14.1.11 1
Prairie Island Unit 1-Amendment No. AA,//,I Prairie Island Unit 2-Amendment No. fe,8b,:
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o UNITED STATES g
_8 NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20655 f
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2
. AMENDMENT TO FACILITY OPERATING LICENSE
' Amendment No.'80 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 July 18, 1988 as supplemented by letters dated September 15,.1988 and March 10, 1989, complies with the standards and requirements of the Atomic Energy Act of.1954, as amended (the Act), and the Commission's rules and regulations
_i 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 1
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 Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
t.' :
2 l
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, 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 h
P Theodore R. Quay, Act'ing Director i
Project Directorate 111-1 Division of Reactor Projects'- III, IV, V
& Special Projects
Attachment:
Changes to the Technical l
Specifications Date of Issuance: April 3,1989 l
l l
l I
k
j ATTACHMENT TO LICENSE AMENDMENTS NOS. 87 AND 80 FACILITY OPERATING LICENSES NOS. DPR-42 AND F M DOCKETS N05. 50-282 AND 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identiffpd by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT TS.2.3-3 TS.2.3-3
.TS.2.3-6 TS.2.3-6 Table TS.3.5-2 (Page 2 of 2)
Table TS.3.5-2 (Page 2 of 2)
Table TS.4.1-1 (Page 2 of 5)
Table TS.4.1-1 (Page 2 of 5)
I l
l l
l
TS.2.3-3 K6- 0.002 for T > T',
O for T < T' T3-10, see f(AI) as defined in d. above,
- f. Low reactor coolant flow per loop - >90% of normal indicated loop flow as measured at loop elbow tap.
- g. Open reactor coolant pump motor breaker.
1 (1)
Reactor coolant pump bus undervoltage -
>75% of normal voltage.
(2)
Reactor coolant pump bus underfrequency -
258.2HZ h' Power range neutron flux rate.
(1) Positive rate - <15% of rated power with a time
- constant >2 seconds (2) Negative rate - $15% of rated power with a time constant >2 seconds 3.
Other reactor trips
- a. High pressurizer water level - <90% of narrow range instrument span,
- b. Low-low steam generator water level - >5% of narrow range instrument span.
- c.
Low steam generator water level - >15% of narrow rangeinstrumentincoinegdencewithsteam/feedwater mismatch flow - $1.0 x 10 lbs/hr.
j
- d. Turbine Generator trip (1) Turbine stop valve indicators - closed (2) Low auto stop oil pressure - >45 psig
- e. Safety injection - See Specification 3.5 B.
Protective instrumentation settings for reactor trip interlocks shall be as follows:
1.
"At Tower" reactor trips that are blocked at low power (low pressurizer pressure, high pressurizer level, and loss of flow for one or two loops) shall be unblocked whenever:
i'
- a. Power range neutron flux is >12% of rated power or,
- b. Turbine load is >10% of full load turbine impulse pressure.
- The low steam generator water level in coincidence with steam /feedwater mismatch trip may be deleted following installation of the digital feedwater control system incorporating the median signal selector function. An acceptable verification and validation program shall be demonstrated to the satisfaction of the NRC Staff.
Prairie Island Unit 1 - Amendment No. 28,87 Prairie Island Unit 2 - Amendment No. 22,80
l TS.2.3-6 g
i The-other reactor trips specified in A.3. above provide additional protection.
l l
The safety injection signal trips the reactor to decrease the severity of the l
accident condition. The reactor is tripped when the turbine generator trips above a power level equivalent to the load rejection capacity of the steam dump J
valves. This reduces the severity of the loss-of-load transient.
The positive power range rate trip provides protection against rapid flux increases which are characteristic of rod ejection events from any power l
1evel. 'specifically, this trip compliments the power range nuclear flux high and low trip to assure that the criteria are met for rod ejection from j
partial power.
The negative power range rate trip provides protection satisfying all IEEE criteria to assure that minimum DNBR is maintained above 1.30 for Exxon Nuclear fuel and above 1.17 for Westinghouse fuel for all multiple control rod drop accidents. Analysis, indicates (Section 14.1.3) that in tMe case of a single rod drop, a return. to full power will be initiated by. the automatic reactor control system in response to a continued full power turbine load demand and it will not result in a DNBR of less than 1.30 for Exxon Nuclear fuel or 1.17 for Westinghouse fuel. Thus, automatic protection for a single rod drop is not required. Admini-strative limits in Specification 3.10 require a power reduction if design power
' distribution limits are exceeded by a single misaligned or dropped rod.
References:
(1) FSAR 14.1.1 (2) FSAR Page 14-3 (3) FSAR 14.2.6 (4) FSAR 14,3.1 (5) FSAR 14.1.'2 1
(6) FSAR 7.2, 7.3 l
(7) FSAR
Prairie Island Unit 2-Amendment No. 88,86,
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