ML19316B186
| ML19316B186 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/27/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19316B182 | List: |
| References | |
| NUDOCS 8006120023 | |
| Download: ML19316B186 (6) | |
Text
O
,(,..,.(o UNITED STATES g
g NUCLEAR REGULATORY COMMISSION y
r wAsMNGTON, D. C. 20665
/
OMAHA PUBLIC POWER DISTRICT e
DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment by Omaha Public Power District (the licensee) dated March 8,1978, October 24, 1978 and September 20, 1979, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, 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 1
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.
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l 80061200 Q
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. 2.
Accordingly, Facility Operating License No. 48 DPR-40 is amended by changes to the Technical Specifications as indicated in the Attachment to this license amendment, by amending paragraph 3.B. and adding paragraph 3.E. to read as follows:
l B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speci-fications.
E.
The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall be described in the station chemistry manual and shall include:
1.
Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to measure the values of the critical parameters; 3.
Identification of process sampling points; 4.
Procedure for the recording and management of data; 5.
Procedures defining corrective actions for off control point chemistry conditions; and 6.
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective actions."
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION obert A.
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 27, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-4C DOCKET NO. 50-285 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Pages 2-73 2-74 2-87
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2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Sutmressors (Snubbers)
Azmlicability Applies to the operability of safety related shock suppressors (snubbers).
Obj ective To specify modes of reactor operation for given conditions of safety related snubbers.
Specifications (1)
During all modes of operation except Cold Shutdown and Re-fueling, all snubbers listed in Table 2-6 shall be operable except as noted in 2.18(2) through 2.18(5) below.
l (2)
From the ti=e that a snubber is determined to be ineperable, continued reactor operation is per=issible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is made operable or replaced prior to that time.
(3)
If the requirements of 2.18(1) and 2.18(2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in a celd shutdown cendition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
(k)
If a snubber is deter =ined to be inoperable while the re-actor is in the shutdown or refueling ku:le, the snubber shan be =ade operable or replaced prior to reactor start-up.
(5)
A snubber may be removed for surve111ance in accordance v::h Section 3.1h(h) of these Technical Specifications, provided the folleving conditions are set:
(a)
A given snubber station shall not be without an ope. able snubber for more than two hours during surveillance of attendant snubber. A coubber =ay be replaced by ar; oper-able snubber during surveillance and repair.
l (b)
No other installed snubber listed in Table 2-6 is biovn to be inoperable.
(c)
Only one sriubber listed in Table 2-6 shall be removed for testing at a time to ensure that no two snubber stations are without an operable snubber during the sarie time interval.
(6)
Snubbers may be added to safety related systems withouc prior licensing amendments to Table 2-6 provided that a revision to Table 2-6 is included in subsequent licensing amendment requests.
Amendment No. g, 48 2-73
- 2. 0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Suptressors (Snubbers) (Continued)
Basis Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while anoving normal thermal motion during startup or shutdown. The consequence of an inoperable snubber is an in-crease in the probability of structural damage to piping as a result of a seismic, or other event, initiating dynamic loads.
It is therefore required that au snubbers required to protect
'l the primary coolant system or any other safety system or compo-neat be operable during reactor operation.
Because the snubber protection is rdquired only during low prob-ability events, an inoperable period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is anoved for a
repairs or replacements and an inoperable period of two hours is allowed for surveillance. In the event that a shutdown is re-quired, the anovance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown con-dition vin permit an orderly shutdown consistent with standard operating procedures. Since plant startup should not ecmcence with knowingly defective safety related equipment, Specification 2.18(k) prohibits startup with inoperable snubbers.
Table 2-6 lists the snubbers that are on safety related systems.
The snubbers that.are listed as " Inaccessible During Nor=al Opera-tion" are located inside of the containment building and would require a significant expenditure in =an-rems to inspect en a periodic basis. "' hose snubbers listed as "Diffiev.1 to Remove for Functional Testing" are so listed because they are either:
(1) rated at grea:er than 50,000 lbs. force, (2) inaccessible due to surroundisg structures, er (3) located such that an excessive ~ amount of time and effort vould be required to renove them for testing.
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i Amendment No. g 46 2-Th 4
TABLE 2-6 (Continued) td Accessible in High Difficult to During Inaccessible Radiation Remove for
- 5nubber Normal During Normal Areas During Functional No.
Elevatien Oeeration Operation Shutdown Testing SIS-162 101k' 6" X
SIS-16k 1014' 0" X
SIS-165 101k' 6" X
SIS-165A 8
Top 101k' 6" X
SIS-165A Bottom 101k' 6" X
SIS-166 101k' 6" X
SIS-167 101h ' 6" X
SIS-168 101k' 6" I
SIS-168A Tcp loik' 6" X
SIS-168A Bottom 101k' 6" X
SIS-169 1007' 7" X
SIS-169A 1007' 7" X
SIS-170 1007' 8" X
SIS-170A 1007' 5" X
SIS-172 1032' 0" X
SIS-173 1036' 8" X
GIS-17h 10k9' 2" X
SIS-likA 10k9' 6" X
SIS-174B 1051' 7-1/k" X
X SIS-17kBB 106k' 6" X
SIS-17kc 1052' 6" X
X SIS-17kD 1063' 7-1/k" X
X SIS-17kE 106k' 6" X
X SIS-175 1057' 0" X
X SIS-175A 1056' 5-1/2" X
SIS-176B 1052' 6" I
X SIS-176C 1051' 7-1/k" X
X SIS-176D 106k' 6" X
X i
SIS-176E 1063' 7-1/k" X
X l
SIS-176G 1074' 0" X
x SIS-176H 10Th' 0" X
X SIS-183 1055' 9-1/2" X
j SIS-18k 979' 6" X
Nbt N W"48 2-87