ML19249A578
| ML19249A578 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/27/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19249A579 | List: |
| References | |
| NUDOCS 7908230654 | |
| Download: ML19249A578 (6) | |
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k UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 o
8 CONSUMERS POWER COMPANY
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DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO~ PROVISIONAL OPERATING LICENSE Amendment No. 50 License No. DPR-20 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licerisee) dated March 6,1979, as supplemented by letter dated May 17, 1979, 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 Comission; 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 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 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.
774170 790823 oc>sy
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No.
DPR-20 is hereby amended to read as follows:
"B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 50, 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 c[.c~((
vcL g, Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 27,1979
ATTACHMENT TO LICENSE AMENDMENT ~NO.~ ~50 PROVISIONAL OPERATING' LICENSE'NO. DPR-20 i
DOCKET'NO. 50-255 Revise Appendix A by removing the pages identified below and inserting the enclosed pages. The revised pages include the captioned amendment number and contain vertical lines indicating the areas of change.
PAGES 3-65 3-66 3-66a 774172
3.
7%CCRE INST?.UMEiTATION Atelicability Applies to tse operability of the in-core instr =entation syste=.
Obiective s
To specif/' the functional and operability require =ents of the in-core instrumentation syste=.
Scecification
~
a.
Sufficient in-core instru=entation sM be operable whenever the reactor is operating at or above 50f rated power (65% of rated power if no dropped or =isaligned rods are present) in order to:
(1) Assist in, the calibration of the out-of-core detectors, and (2)
Chee'. gross core power distribution. As a =ini_u=, 50f, cf.the in-ccre detec crs and :nt less than 10 individual detectors per quadrant, which shall include two detectors at each of the axial levels, shall be operable.
b.
For pcVer operatice above 85% of rated power, in-core detector alar =s generated by the data logger shall be set, based on the latest power iistribution obtained, such that the p%k linear power does ct exceed the limit specified in Sectic: 3.10.3.a.
If fcur or =cre coincident alar =s are received, the validity of the alar =s shall be i=ediately deter =in'ed and, if valid, power shall be i=ediately decreased below alar = se: point and a power distribution cap obtained.
If a pcver distribution is not obtained within 2h hours of the alar = conditions, pcver shall be reduced to 85% of rated pover.
c.
T e in-core detector alar = set points shall be established, tased on the latest power distribution caps, nor=alized to the kW/ft.li=it defined in Section 3.10 3.a.
d.
?over distributions s%
be evaluated every week or =cre ofte= as.
required by plant operations.
e.
Tne data logger can be inoperable for two hours.
If at the end of two -
hours it is not tvailable, the pcuer level scall not exceed 55% of rated pcVer.
f.
If the data legger fer the in-:cres is :: in Operatic: for : re than ve hcurs and reacter pcVer is a: er above 3C5 ef rated power (555 Of raced.: ver if no ir:pped er risaligned rois are present;, readings s e ' ' b e zake: e.:t ' gged := a ' ' u=
f '.I i:Liviinal ieze:::rs per quadra:: (:: include at 'eas: 5I5 Of the :::a1 :=cer of ie:e:: rs in e, n,i a. ( 3
.;m (a
5-65 Amendment No. 37, 50
3 11 IN-CORE INSTRUMENTATION (Contd)
Soecification (Contd) a 10-hour period) at least each two hours thereafter or the reactor power level shall be reduced to less than 50% of rated power (65% of rated power if no dropped or =isaligned rods are present).
If read-ings indicate a local power level equal to or greater than the alar =
set point, the action specified in 3.11.b shall be taken.
A and F,,T shall be deter =ined whenever the core power distribution.__
g.
Fr
^
A T
is evaluated. If either F or F is found to be in excess of the r
r li=it specified in Section 3.10.3.s; vithin six hours ther=al power shall be reduced to less than [(1.77 + Fr ) x 2530 MW l or ((1.h5 +
t A
r ) x 2530 MW }, whichever is lover.
F Basis A system of 45 in-core flux detector and therroccuple assemblies and a data display, alarm and record functions has been provided. A four level, five level or six level system may be used. (1)(2) The out-of-core nuclear instrumentation calibration includes:
._.m-Calibratica (axial and a i=uthal) of the split detectors at initial re-a.
acter start-up and during the power escalation progra=.-
b.
A co=parisen check vith the in-core instru=entation in the event abnormal readings are observed on the out-of-core detectors during. operation..
c.
Calibration check during subsequent reactor start-ups...
d.
Confir= that readings frc= the out-of-core split detectors are. as expected.
Core power distribution verification includes:
a.
Measure =ent at initial reactor start-up to check that pcVer distribu tien is consistent with calculations.
b.
Subsequent checks during operation to insure that power. distribution.
is consistent with calculations.
c.
Indication of power distribution in the event that abnormal situa-tiens occur during reactor operation.
If the data 1cgger for the in-core readout is not in operation for =cre than tvo hours, power vill be reduced to previde rJLrgin between the actual peak linear heat 6eneration rates and the li=it and the in-core readings vill be w ually collected at the ter=inal blocks in the centrol roc =
utilizing a suitable signal detector.
If this is net feasible with the 3-66 Amendment No. 31, 43,.Ci
e 3.11 IN-CORE INSTRUME2TIATICN (Contd)
-- _ _-- - - - _ _ I _.
Basis (Contd)
=anpover available, the reacter power vill be reduced further to nini=1:e the probability of exceeding the peaking factors. The time interval of two hours and the mini =um of 10 detectors per quadrant are sufficient to caintain adequate surveillance of the core pcVer distri-bution to detect significant changes until the data legger is returned to service.
Beference (1) FSAR, Section 7.k.2.k.
(2) Letter dated May 17, 1979 from D. Hof fman, Consumers Power Company to D. Ziemann, Nuclear Regulatory Commission.
7741.73 3-66a Amend =ent No. 43,50