ML18079B083
| ML18079B083 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/26/1979 |
| From: | Librizzi F Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| LCR-79-13, NUDOCS 7910100306 | |
| Download: ML18079B083 (7) | |
Text
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PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 Ref. LCR 79-13 September 26, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Albert Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment and our analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station, Unit No. 1.
This request consists of a proposed change to the Safety Technical Specifications (Appendix A) involving changes to the reactor trip setpoint table.
This change involves a single safety issue, has acceptability for the issue clearly identified by an NRC position, and is deemed not to involve ~ significant hazards consideration.
Therefore, it is determined to be a Class III amendment as defined by 10CFR 170.22 and a check for the amount of $4,000.00 is enclosed.
This submittal includes three (3) originals and forty (40) copies.
Enclosures Very truly yours,
~
Frank P. L~~
General Manager -
Electric Production 95-2001 (200M) 2-78
Ref. LCR 79-13 U.S. NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-272 PUBLIC SERVICE ELECTRIC AND GAS COMPANY FACILITY OPERATING LICENSE NO. DPR-70 NO. 1 UNIT SALEM GENERATING STATION Public Service Electric and Gas Company hereby submits proposed changes to Facility Operating License No. DPR-70 for. Salem Gen-erating Station, Unit No. 1.
This change request relates to Safety Technical Specifications (Appendix A) of the Operating License, and pertains to changes in the reactor trip setpoints for Power Range, Neutron Flux, High Positive and High Negative Rate.
Respectfully submitted, PUBLIC SERVICE ELECTRIC AND GAS COMPANY By: ~A)~
FREDERICK W. SCHNEIDER VICE PRESIDENT
Ref. LCR 79-13 STATE OF NEW JERSEY)
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SS:
COUNTY OF ESSEX
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FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the request for change to FACILITY OPERATING LICENSE NO. DPR-70.
The matters set forth in said change request are true to the best of my knowledge, information, and belief.
Subscribed and sworn to before me th.is
, 1979.
Jd_~~ ~
N0tary Pubiic of New Jersey My Commission expires on <!/ £. /,,. / f1 d.!
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e PROPOSED CHANGE REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS TECHNICAL SPECIFICATIONS SALEM UNIT NO. 1 Description of Change Change the Power Range, Neutron Flux, High Positive Rate Trip Setpoint time constant to ~ 1 second.
Change the Power Range, Neutron Flux, High Negative Rate Trip Setpoint to S
3% of rated thermal power with a time constant of > 1 second.
Reason for Change To assure that all dropped control rods (including any single dropped rod) will result in a reactor trip via the Negative Rate Trip function.
Safety '~Evaluation This change will ensure that the minimum DNBR is maintained above 1.30 for all rod drop accidents.
This value is con-sistent with the FSAR and the bases of the technical speci-fications.
Therefore, this change does not constitute an unreviewed safety question as defined by 10 CFR 50.59.
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TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT
- 2. Power Range. Neutron Flux
- 3. Power Range, Neutron Flux, High Positive Rate
- 4. Power Range. Neutron Flux.
High Negative Rate
- 5. Intermediate Range, Neutron Flux
- 6. Source Range, Neutron Flux
- 7. Over temperature JH B. Overpower b.T
- 9. Pressurizer Pressure--Low
- 10. Pressurizer Pressure--High TRIP SETPOINT Not Applicable Low Setpoint - < 253 of RATED THERMAL POWER -
High Setpoint -.::.. 109% of RATED THERMAL POWER
< 5% of RATED THERMAL POWER with a time constant >;&seconds 3
-1
< :&% of RATED THERMAL POWER with a time constant >~:seconds
-.1
< 25% of RATED THERMAL POWER
< 105 counts per second See Note 1 See Note 2
~ 1865 psig
~ 2385 psig
- 11. Pressurizer Water Level--Uigh
< 92% of instrument span
- 12. Loss of Flow
_:: 90% of design flow per loop*
- Design flow is 88,500 gpm per loop.
ALLOWABLE VALUES Not Applicable Low Setpo1nt - < 26% of RATED THERMAL POWER -
High Setpoint - < 110% of RATED THERMAL POWER
< 5.5% of RATED THERMAL POWER with a time constant > :( seconds
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- 3*.5"".
< ~
of RATED THERMAL POWER with a time constant > ~seconds
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< 30% of RATED THERMAL POWER
.::.. 1.3 x 105 counts per second See Note 3 See Note 3
~ 1855 psig
~ 2395 psig
.::.. 93% of instrument span
> 89% of design flow j)er loop*
LIMITING SAFETY SYSTEM SETTINGS BASES A~.J,*11.t:Jt--I lo Intermediate and Source Range, Nuclear Flux fJ/e. B 2 -1 The Intennediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup. These trips provide redundant protection to the low setpoint trip of the Power Range, Neutron Flux channels+S The Source Range Channels will initiate a reactor trip at about 10 counts per second unless manually blocked when P-6 becomes
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active.
The Intermediate Range Channels will initiate a reactor trip at
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a current level proportional to approximately 25 percent of RATED THERMAL POWER unless manually blocked when P-10 becomes active.
No credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses; however, their functional capability at the specified trip settings is *required by this specification to enhance the overall reliability of the Reactor Protection System.
Overtemperature ~T The Overtemperature ~T trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the High and Low Pressure reactor trips. This setpoint includes corrections for changes in density and heat capacity of water with temperature and dynamic com-pensation for piping delays from the core to the loop temperature detectors. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2. 1-1.
If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically*reduced according to the notations in Table 2.2-1.
SALEM - UNIT l B 2-4
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Proposed addition to page B2-4 The Power Range Negative Rate trip provides protection to ensure that the minimum DNBR is maintained above 1.30 for rod drop accidents.
At high power a single or multiple rod drop accident could cause local flux peaking which when in conjunction with nuclear power being maintained equivalent to turbine.power by action of the automatic rod control system could cause an unconservative local DNBR to exist.
The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rods.