ML20203N287
| ML20203N287 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/10/1986 |
| From: | Sells D Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8609230286 | |
| Download: ML20203N287 (5) | |
Text
y Septemb r-10, 1986'
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Docket No. 50-285 Distribution:
Pkreutzer NRC & L PDRs Branch Files OGC-Bethesda-DSells.
Mr. R. L..Andrews EJordan:
JPartlow Division Manager - Nuclear Production BGrimes ACRS Omaha Public Power District-FMiraglia Docket Files 1623 Harney Street Omaha, Nebraska 68102_
Dear Mr. Andrews:
In response to a verbal request that I made to Ms. Munderloh of your staff, OPPD provided a working copy of your Technical Specifications to be compared-to the NRC's record copy. Two discrepancies and an error that is present in both your working copy and the NRC's record copy were noted.
The two discrepancies were probably made when the pages were retyped.
'These can be corrected by making the following changes to your working copy.-
Page 3 Basis, second line, word "results" should be " result".
Page 3 3.3.b. third line, third word "is" should be "in".
Errors-of this type should be eliminated since instituting the policy of submitting marked up technical specification pages as opposed to retyped pages.
I might add that the submittal of marked up pages makes the editing job a great deal easier.
An error occurs on page 3-70 Section 3.12.1.f in the fourth line, "which" is misspelled as "shich". This is an error in the NRC record copy and should be changed in a future application, preferably one that would affect this page for other reasons.
This Technical Specification comparision covered the posting' of amendments through Amendment No. 98 since Amendment No. 99 had not been posted to your working copy at the time of the request.
i This comparison was done by Pat Kreutzer, the Project Directorate Licensing Assistant.
I join her in thanking you for your prompt response to my verbal request and the excellent results of this comparison.
Sincerely,
/S/
8609230286 060910 Donald E. Sells, Project Manager PDR ADOCK 05000285 PWR Project Directorate #8 P
PDR Division of PWR Licensing-B
Enclosures:
TS Pages cc w/ enclosures:
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See next page t
PWRip P
PWR#8 Pylnstzer D
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Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District Unit No. 1 l
cc:
Harry it. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Metropolitan Planning Agency ATTN:
Dagnia Prieditis 7000 West Center Road Omaha, Nebraska 68107 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health Department of Health 301 Centennial Hall, South P.O. Box 95007 Lincoln, Nebraska 68509
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V 3.0 SURVEILLANCE REQUIREMENTS
~.1 Instrumentation and Control 3
Applicability Applies to the reactor protective system and other critical instru-mentation and controls.
Objective To specify the minimum frequency and type of surveillance to be applied to critical plant instrumentation and controls.
Specifications Calibration, testing and checking of instrument channels, reactor protective system and engineered safeguards system logic channels and miscellaneous instrument systems and controls shall be performed as specified in Tables 3-1 to 3-3 subject to the following:
a.
A maximum allowable extension not to exceed 25%
of the surveillance interval unless otherwise specified, and b.
A total maximum combined interval time for any 3 consecutive surveillance functions not to exceed 3.25 (g
times the specified interval.
Basis 9
Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which result [in " upscale" or "downscale" indica-Y tion can be easily recognized by simple observation of the functioning of an instrument or system. Furthemore, r.uch failures are, in many cases, revealed by alarm or annunciator action and a check supple-ments this type of built-in surveillance.
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Based on the District's experience in operation of conventional power plants and on reported nuclear plant experience, a checking frequency of once-per-shift is deemed adequate for reactor and steam system instrumentation.
Calibrations are performed to ensure the presentation and acquisition of accurate information.
The power range safety channels are calibrated daily against a calorimetric balance standard to account for errors induced by changing rod patterns and core physics parameters.
Other channels, subject only to the " drift" errors, can be expected to remain within acceptable tolerances if recalibration is performed at each refueling shutdown interval.
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t' 3-1 Change No. 9 August 23. 197k
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3.0 SURVEILI.ANCE REQUIREMENTS 3.3 Reactor Coolant System. Steam Generator Tubes, and Other Components
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to ASME XI Boiler & Pressure Vessel Code Inspection and Testing Subject Surveillance (Continued) mode every time the plant is placed in the cold shutdown condition for refueling, each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to return-ing the valve to service after maintenance, repair or re-placement work is performed.
Whenever the integrity of a pressure isolation valve listed b.
in Table 2-9 cannot be demonstrated the integrity of the leaking valve shall be % each high pressure line having a remaining valvedetermined and recorded daily. In addition, the position of of other valve located in the high pressure line shall be reo6rded daily.
f' Ac:endment No. 46, Order dated 4/20/81 3-26
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' '3.0 SURVEILLANCE REQUIRDGNTS r
3.12 Radiological Waste Sampling and Monitoring (Continued)
C 3.12.1 Liquid and Gaseous Effluents (Continued)
(iii) Quarterly channel functional tests.-
(iv)
Channel calibration at "R" frequency (every 18 months).
e.
The steam generator blowdown effluent flow iate will be calibrated at "R" frequency (every 18 months) and visually detonained operable daily.
f.
Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time overGRgg each discharge occurred. Analytical results shall be submitted to the Ccemission in accordance with Section 5.9.4.a of these specifications.
(2) Gaseous Effluents a.
Radioactive gaseous vaste sampling and activity analyses shall be performed in accordance with Table 3-12.
The results of these analyses shall be used with the calculational methods in the ODCM to assure that the concentration of radioactive materials in unrestricted areas is limited to the values in Specification 2.9 1(2)a.
b., (i)
A ventilation stack radiation monitor shall have a source check prior to any release of radioactive materials from a gas decay tank or the containment. A monthly source check will be performed during refueling outages if a purge or gas decay tank release is not done during that month.
(ii)
Each ventilation stack monitor shall have a quarterly channel functional test.
(iii) Each ventilation stack monitor shall.be calibrated at "R" frequency (every 18 months).
(iv)
The ventilation stack flow rate vill be calibrated and functionally tested at "R" frequency (every 18 months).
The stack radiation monitor flow rate will be calibrated and functionally tested at "R" frequency (every 18 months).
Both will be determined operable by visual inspection daily.
c.
The condenser air ejector monitor shall have a:
(i)
Daily channel check.
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(ii)
Monthly source check.
3-70 Amendment No. 86 I
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