ML20029C376
| ML20029C376 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/19/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20029C372 | List: |
| References | |
| NUDOCS 9103270236 | |
| Download: ML20029C376 (8) | |
Text
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'S UNITED STATES 3! ' ' ' '
NUCLEAR REGULATORY COMMISSION
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WASHINoToN, O C. 20066 t
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OMAHA PUBLIC POWER DISTRtrT, DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACillTY OPERATING LICENSE q
Anerdment No.138 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for omendment by the Omaha Public Fower District (the licensee) dated June 28, 1990, as supplemented December 20, 1990, complies with the standards and re Energy Act of 1954, as an.tnded (the Act)quirements of the Atomic
, and the Comission'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:
(1) that the activities authorized by this amenor.;ent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in complionce with the Comission's regulations; D.
The issuance of this license amendnent 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 satisfieo.
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Accot dingly, Facility Operat;ng License No. OPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.138, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 60 days from the date of issuonce.
TOR THE NUCLEAR REGULATORY COMMISSION 9
mpu h u ut my Theodore R. Quay, Director Project Directorate IV-1 Division of Redctor Projects Ill, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 19, 1991
' ATTACHMENT TO LICENSE A!!ENDMENT NO. Su FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Apg ndix "A" Technical Specifications as indicated below. The revised pages are identified by arnendment number and contain vertical lines indicating the 6rea of change, REMOVE PAGES-INSERT PAGES 2-30 2-30 2-31 2-31 2-31a 3-17a 3-17a 4
3-20e s
4 I 6
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F 2.0 LIMITING CONDITIONS FOR OPERATION 2.6 Containment System ADolicability Applies to the reactor containment system.
Obiective To assure the integrity of the reactor containment system.
Soecifications (1) Containmtnt Intearity a.
Containment integrity shall not be violated unless the reactor is in the cold shutdown condition.
b.
Containment integrity shall not be violated when the reactor vessel head is removed if the boron concentration is less than refueling concentration, c.
Except for testing one CEOM at a time, positive reactivity changes shall not be made by CEA motion or boron dilution unless the containment integrity is intact.
d.
Prior to the reactor going critical after a refueling outage, an administrative check will be made to confirm that all " locked closed" manual containment isolation valves are closed and locked.
e.
The containment purge isolation valves will be locked closed unless the reactor is in a cold or refueling shutdown condition.
(2)
Internal Pre nyf_q
.The internal pressure shall not exceed 3 psig (except for containment leak rate tests).
(3) Hydroaen Purae System a.
Minimum Reouirements The reactor shall not be made critical unless all of the following requirements are met:
~
1.
'The containment isolation valves VA-280 and VA-289 shall be locked closed.
2.
VA-80A and VA-808 with associated valves and piping to include VA-82 filters, are operable.
Amendment No. EE,138 2-30
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2.0 LIMITING CONDITIONS FOR OPERATION
-2.6 Containment System (Continued) b.
Modification of Minimum Recuirements After the reactor has been made critical, the minimum requirements may be modified to allow either or both of the following stnaments (1,ii) to be applicable at any one time.
If the operability of the component (s) is not restored to meet the minimum requirements within the time specified below, the reactor shall be placed in a hot shutdown condition within six hours.
(i) One of the hydrogen purge fans, VA-80A or VA-808, with associated valves and pi)ing may, be inoperable provided the fan is restored to opera)le status within 30 days.
(ii) The hydrogen purge filter system, VA-82, may be inoperable provided the system is restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Basis The reactor coolant system conditions of cold shutdown assure that no steam will be formed and, hence, there would be no pressure buildup in the containment if the reactor coolant system ruptures.
The shutdown margins are selected based on the type of activities that are being carried out.
The refueling boron concentration provides a shutdown margin which precludes criticality under any circumstances.
Each CEDM must be tested and some-have two CEA's attached.
Regarding internal pressure limitations, the containment design pressure of 60 psi would not be exceeded if the-intern of-coo $antaccidentwereasmuchas3psig.})pressurebeforeamajorloss-The containment integrity will be protected if the visual check of all " locked closed" manual isolation valves to verify them closed is made prior to plant start-up after an extended outage where one or more valves could inadvertently be left open. Operation of the purge inution. valves is prevented during normal operations due to the size of the valves-(42 inches) and a concern about-their ability to close against the differential pressure that could result from a LOCA or MSLB.
The Hydrogen Purge System is required to be operable in order to control thequantity)ofcombustiblegasesincontainmentinapost-LOCA condition.\\
-The containment integrity will-be )rotected by ensuring the penetration-valves VA-280 and VA-289 are "locced closed" while HCV-881 and HCV-882 are normally closed during-power operation. The applicable
. surveillance testing requirements of Table ~3-5 will ensure that the system is capable of performing its design function.
The blowers (VA-80A and VA-808), associated valves, and piping are single failure proof, have been designed as a Seismic Class I System, and are redundant to the VA-82 filter header.
VA-80A or VA-808 is capable of providing sufficient hydrogen removal capabilities as required by the USAR to prevent the hydrogen concentgation inside of containment from exceeding the 4% flamability limit \\ >
Electrical Equipment qualification was not required as the radiation-doses in the area of belowtheminimumrequirements.gHydrogenPurgeSystemequipmentwere Amendment No. f)B,138 2-31
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'O 2.0 LIMITING CONDITIONS FOR OPERATION 2.6 Containment System (Continued)
VA 80A or VA-80B with the associated valves and piping may be inoserable for 30 days.
The redundancy of the blowers allows one blower wita associated valves and piping to be removed from operation while the other train has the capability to provide 100% hydrogen control.
References (1) USAR,.Section 14.16; Figure 14.16-2 (2) Regulatory Guide 1.7(1971)
(3)
USAR, Section 14.17 (4)
Engineering Study 86-10, Calculation 53 I
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Amendment No. 138 2-31a L
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3.0 SURVEILLANCE REOUIREMENTS 3,2
- Equipment and Sampling Tests (continued)
The Safety Injection (SI) pump room air treatment system consists of charcoal adsorbers which are installed in normally bypassed ducts. This system is designed to reduce the potential release of radiolodine i_n SI pump rooms during the recirculation period following a DBA, The in place and laboratory testing of charcoal adsorbers will assure system integrity and performance.
Pressure drops across the combined HEPA filters and charcoal adsorbers, of less than 9 inches of water for the control room filters (VA 64A & VA 64B) and of less than 6 inches of water for each of the other air treatment systems will indicate that the filters and adsorbers are not clogged by amounts of foreign matter that would interfere with performance to' established levels. Operation of each system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month will demonstrate operability and remove excessive moisture build up in the adsorbers.
The hydrogen purge system provides the control of combustible gases (hydrogen) in containment for a post-LOCA environment. The surveillance tests provide assurance that the system is operable and capable of performing its design function. VA 80A or VA-80B is capable of controlling the expected hydrogen generation (67 SCFM) associated with 1) Zirconium-- water reactions,2) radiolytic decomposition of sump water and 3) corrosion of metals within containment. The system should have a minimum of one blower with associated valves and piping (VA-80A or VA 80B) available at all times to
, meet the guidelines of Regulatory Guide 1.7 (1971).
The requirements in 2.9.l(2)f(iii) to automatically isolate the hydrogen purge system by the. stack radiation monitors does not apply in that the isolation valves do not have automatic isolation capability.
If significant painting,Tfire or chemical release occurs such that the HEPA filters or charcoal adsorbers could~become contaminated from the fumes, chemicals or foreign materials,- testing will be performed to confirm system performance.
Demonstration of the automatic and/or manual initiation capability will assure the-
- system's availability.
References USAR, Section 9.10 317a Amendment No.A'J,67,N28,138 i.
Table 3-5 l
(Cbntinued) l 1
I Test ns-7_=ncy l
1 I
- 17. IbW Purge System (l)
- 1.. Verify all m nual valves are operable by During each refueling cutage l
i ompleting at least one cycle.
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2.
Cycle eacti automatic valve thrugh at least During each refueling cutage l
cne amplete cycle of full travel frm the
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control room. Verification of the valve l
cycling may te determined by the cbservation I
of position indicating lights.
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I 3.
Initiate flow through the VA-80A and VA-BOB blowers, l
HEPA filter, a:ti charcoal adsoners and verify l
that the systes ::perates for at least l
(a) 30' minutes with suctist from the auxiliary a) Monthly I
building (Roon 59)
(b) 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with suctist from the cmtainment l
b) During each reftaeling outage !
I 3
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4.
Verify the pressure drop across the VA-82 During endt reftmling t=*=r=
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HEPAs and charcoal filter to be less than 6 inches l
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of water. Verify a system flow rate of greater than l
C 80 scos and less than 230 W during system operation l
W en tested in accordance with 3b. above.
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I (1)
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'Ihe requirements of T.S. requirement 2.9.1(2)f(iii) do not apply.
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Amerrkment No.
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