ML20245L283

Amend 121 to License DPR-40,modifying Tech Specs to Change Containment Spray Sys Surveillance Testing Requirements to Provide Quantitative Value for Min Acceptance Criteria & Reducing Max Power Level on Figure 2-7

ML20245L283
Person / Time
Site:	Fort Calhoun
Issue date:	04/26/1989
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245L270	List: ML20245L267 ML20245L283 ML20245L290
References
NUDOCS 8905050361
Download: ML20245L283 (9)

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.$g UNITED STATES f

y a NUCLEAR REGULATORY COMMISSION 5 l WASHINGTON, D. C. 20555

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OMAHA PUBLIC PCWER DISTRICT DOCKET fiC. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDHENT TO FACILITY OPERATING LICENSE '

Amendment No.121 License No. DPR-40

1. The Fuclear Regulatory Corrission (the Connission) has found thet:

A. The applicaticr. fer amendment by the Cnha Public Power District *

(the licensec) dated January 6,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissicn's rules and regulations set focth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the previsions of the Act, and the rules and regulations of the Cerrission; C. There is reescrable assurance: (i)thattheactivitiesauthericd

. by this amendn.cnt can be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in compliance with the Comission's regulations; D. The issuance of this license amendment will ret be ininiical to the concn defense and security or to the health ano safety cf the public; and E. The issuance of this amendment is in acccrdance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes j to the Technical Specifications as indicated in the attachment to this I license amendment, and paragraph 3.B. of Facility Operating Licensc No, i DPR-40 is hereby amended to read as follows: i B. Technical Specifications-The Technical Specifications contained in Appendix A, as revised through Amendment No.121, are hereby incorporated j in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective es of its date of issuance with iull-implementation within 30 days from the date of it uance.

FOR THE NUCLEAR REGULAT0r,Y COMMISSION g

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Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Prcjects Office of Nuclear Reactor Regulation

Attachment:

Char.ges to the Technical Specifications Date of Issuance: April 26, 1989 I 1

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ATTACHMENT TO LICEf!SE AMENLf;ENT fl0.121 FACILITY OPERATIf!G LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 2-6 2-6 Figure 2-3 Figure 2-3 Figure 2-7 Figure 2-7 3-54 3-34 57 3-57 3-57a '

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2.0 LIMITING CONDITIONS FOR OPEhATIOR 2.1 ReactorCoolantSystem(Continued) 2.1.2 Heat _upandCccldownRate(Continued) 1500 MWt and 80% load factor. The predicteo shift at this location at the 1/4t depth from the inner surface is 332'F, including margin, and was calculated using.the shift prediction equation of the proposed Regulatory Guide 1.99, Revision 2. The actual shift in T will be re-established periodically during the plant operaticn by tesbg of reactor vessel material samples which are irradiated cumulatively by securing them near the inside wall of the reactor vessel as describeo in Section 4.5.3 ano Figure 4.5-1 of the USAR. To compensate for any increase in the T caused by irradiation, liraits on the pressure-temperature relation 0Ip are periodically changed to stay within the stress limits during heatup and cooldown. Analysg)of the second removed irradiated reactor vessel surveillance specimen , combined with welo chemical composition data ano reduced core leading desist.s initiated in Cycle 8, indicated that

. .thefiuenceattheenoo{gl4.0 Effective Full Power Years (EFPY) at 1500 MWt will be 1.21x10 n/cm' on the inside surface of the reactor l vessel. This results in a total shift of the RT of 285'F, inclucirg trargin, for the 6rea of greatest sensitivity (webiretal) at the 1/4t location as determined from Figure 2-3. Operation thrcugh fuel Cycle 1,5 will result in less than 14.0 EFPY.

The limit ifnes in Figures 2-IA and 2-1B are based on the following:

A. Heatup and Cooldown Curves - From Section III of-the ASME Code, Appendix G-2215.

Kyp=2Kyg + KIT KIR = Allowance stress intensity factor at temperature  ;

related to RTNDT (ASME III Figure G-2110.1). i K

yp'

= Stress intensity factor for membrane stress (pressure).

The 2 represents a safety factor of 2 on pressure.

K = Stress intensity factor radial themal gradient.

IT The above equation is applied to the reactor vessel beltline.

For plant heatup the thermal stress is opposite in sign from the pressure stress and consideration of a heatup rate would allow for a higher pressure. For heatup it is therefore conservative to consider an isothermal heatup or K = 0.

IT For plant cooldown thermal and pressure stress are additive.

I 2-6 Amendment No. 22,#7,5#,7#,77, 199,II#,121 1

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a PREDICTED RADIATION INDUCED NDTT SHIFT FORT CALHOUN REACTOR VESSEL BELTLINE 500 400

/ p 300 l.D. SHIFT

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INCLUDING MARGIN /

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/ 1/4t SHIFT INCLL' DING WARGIN 200

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l 100 2 3 4 5 6 789 2 3 4 1E18 1E19 5E19 Neutron Fluence, n/cra 2 l

FORT CALHOUN FIGURE TECHNICAL SPECIFICATIONS 2-3 Amendment No. JA,77,JES,JJf,121 1

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forDNBHonitoring FortCalhounStation-UnitNo.i 2-7 Amendment No. E,2$,32,A7,7p,77,121 .

a 3.0 SURVEILLANCE . REQUIREMD;T.S.

3.6 Safety injectier, anc Containtrent Cooling.!) stems Tests Applicability I j

Applies to the safety injection system, the containment spray system, J the containment cooling system and air filtration system inside the containment.

Objective To verify that the subject systems will respond proniptly anc perform their intended functions, if required.

Specifications I (1) Safety Injection Systym ,

1 System tests shall be perforraed at each reactor refueling interval.

A test safety feature actuation signal will be applied to initiate operation of the system. The safety injcetion and shutdown .

coolir.g systen. purcp r.:otors may be de-energized for this portion of the test.

A second overlarpir.9 test will be considered satisfactory if control board indication and visual observations ir;oicate all feature actuation signal components heve received in the proper sequence the safety (i.e., the appropriate pun.p and timing breakers shall have opened and closed, and all valves shall have conipleted their travel).

(2) Containment Spray System ,

a. System tests shall be performed at each reactor refueling interval. The test shall be performed with the isolation valves in the spray supply lines at the containment blocked closed. Operation of the system is initiated by tripping the normal actuation instrumentation.

b. At least every five years the spray nozzles shall be verified to be open.

c. The test will be considered satisfactory if:

(1) Visual observations indicate that at least 264 nozzles per spray header have operated satisfactorily.

(ii) No more than one nozzle per spray header is missing.

d. Undisturbed samples of Trisodium Phosphate Dudecahydrate (TSP) that have been exposed to the satte erivironniental conditions as that in the mesh baskets shall be tested on a routine basis once per refueling outage or at least once every 18 months by:

3-54 Amendment flo. ##,121 l

e 3.0 SURVEILLANCE REQUIREMENTS 3.6 Safety Injection and Containment Cooling Systems Tests (Continued) that the spray piping and ccrzles are cpen will be rade initially by a smoke test or other suitably sensitive methcd, and at least every five years thereafter. A single containment spray header flow rate of I 3155 gpmg atomized spray is required to provide the containtnent response specified in Section 2.4 of the Technical Specification:

To achieve the 3155 gpn. flow rate, no greater that ten (10) spray nozzles may be inoperable of which no more than one may be missing.

Since the material is all stainless steel, normally in a dry condition, with no plugging mechanism available, the retest every five years is i

-considered to be more than adequate. {

I Other systems that are also.important to the emergency cooling function '

are the SI tanks, the component cooling system, the raw water system and the containment air coolers. The SI tanks are a passive safeguard.

In accordance with the specifications, the water volume and pressure in the SI tanks are checked periodically. The other systems mentioned operate when the reactor is in operation and are continuously monitored for satisfactory performance. .

The in-containment air treaternt system is designed to filter the containment butiding atmosphere.during accident conditions. Both in-containment ' air treatment systems are cesigned to automatically H start upon accident signals. Should one system f ail to start, the reoundantsystemisdesigneotosgtautomatically. Each of the two '

systen.s hLs 100 percent capacity }

High efficiency' particulate air (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iocine adsorbers, i The charcoal adscrbers are installed to reduce the potentfal release of radiofodine to the environment. The laboratory carbon sarple test results shculd indicate a racicactive methyl iocice removal efficiency of at least 85 percent. If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses util be less than the 10 CFR Part 100 guidelines for the. accidents analyzed.

Pressure drop across the combined HEPA filters and charcoal adscrbers of less than 6 inches of water will indicate that the filters and adsorbers are not clogged by excessive amounts.of foreign matter.

If significant painting, fire or chemical release occurs in a ventilation zone communicating with the system that could lead to the degradation of charcoal adsorbers or HEPA filters, testing will be performed to assure system integrity and performance.

3-57 Amendment No. U ,121

3.0 SURVEILLANCE REQUIREMENTS 3.6 Safety _ Injection.6no.Contaitu r.t Coolino Systems. Tests (Continued)

Operation of the 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 of the filters and adsorbers system and reinove utessive i noisture build-up on the adsorbers.

Demonstrator of the automatic ir.itiation capability will assure system availability.

References (1) USAR, Section 6.2 (2 USAR, Section 6.3 (3 USAR, Section 14.16 (4 USAR, Section 6.4 1

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i 3-57a Amendment No.121 L-____--_-____