ML20142A014

Amend 110 to Liense NPF-1,changing Tech Specs to Revise Surveillance Requirements for Axial Flux Difference,Reflect Change to Fire Pump Diesel Engine Surveillance Requirement & Make Editorial Changes

ML20142A014
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/03/1986
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20142A011	List: ML20142A010 ML20142A014 ML20142A016
References
NUDOCS 8603190220
Download: ML20142A014 (12)

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, f,, UNITED $TATES NUCLEAR REGULATORY COMMISSION s s WASHINGTON, D. C. 20555 s 1

%, .....f PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. NPF-1

1. The Nuclear Regulatory Commission (the Ccmmissioni has found that:

A. The applications for amendment by Portland General Electric Company, et al., (the licensee) dated May 2, 1985, as amended September 6, TU8 E and June 14, 1985, comply 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 Commission; 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 Commission's regulations; -

D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable reauirements have been satisfied.

9603190220 860303 PDR ADOCK 05000344 p PDR

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.110 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

3. This license amendment is effective as of the date of its issuance.

FOR THE NilCLEAR REGULATORY COMMISSION Ti N s N; s t..o -

, Steven A. Varga, Director

• PWR Project Directorate No. 3 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specifications Date of Issuance: March 3, 1986 l

o ATTACHMENT TO LICENSE AMENDMENT N0.110 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-344 Revise Facility Operating License as follows:

Remove Page Insert Page 5 5 Revise Appendix A as follows:

Remove Pages Insert Pages B 3/4 1-1 B 3/4 1-1 3/4 2-2 3/4 2-2 3/4 4-19 3/4 4-19 3/4 4-20 3/4 4-20 3/4 7-25 3/4 7-25 3/4 7-38 3/4 7-38 Figure 5.1-2 Figure 5.1-2 5-5 5-5 l

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(7) Quality Assurance '

Except for the installation of the hancers, restraints a.d' snubbers identified in item A.I of Enclosure 1 to this license, which may be corpleted in accordance with the

- Cuality Assuran Program for Construction, all activitie:;

to which a cuality assurance prograra is applicable shall, after the date of issue of this license, be conducted in accordance with the t!uclear Quality Assurance Program.

2.C(8) The licensee may proceed with and 11 required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.18 of the NRC's Fire Protection Safety Evaluation Report on the Trojan Nuclear Plant Qe/g dated March 22, 1978. These g 7. ,y1

, org modifications shall be completed by the end ~ 3 '9~73 of the second refueling outage of the Trojan facility and prior to return to operation for Cycle 3. In addition, the ifcensee shall submit the additional infomation identified in Table 3.2 of this safety Evaluation Report in accordance with the schedule contained therein. In the event these dates for .

submittal cannot be met, the licensee shall submit a report explaining the circumstances, together with a revised schedule.

(9) Primary Shielding Modification gg ptR The licensee is authorized to modify the primary N/

shielding design as described in PGE letter dated April 22,1977, as supplemented and amended by letters 9i O 615'I dated September 22 and 23,1977 December 22, 1977, January 4 and 24,1978, March 20 and April 4,1978.

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s Amendment No. 110 i

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3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be naintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTOOWN MARGIN of 1.6% ak/k is initially required to control the reactivity transient. Accordingly, the SHUTDDWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. With Tavg less than 200*F, the most restrictive reactivity transients resulting f rom the postulated Boron Dilution Accident are such that a 1.6% ak/k SHUTOOWN MARGIN is initially required.

3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,900 cubic feet in approximately 33 minutes. The reactivity change rate associated with boron reductions will therefore be within th.e capability for operator recognition and control.

3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)

The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning, middle, and near the end of each fuel cycle is adequate to confirm the MTC value since this coef ficient changes slowly due TROJAN-UNIT 1 B 3/4 1-1 Amendment No. 64, 110

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

b. THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the 15% target band and ACTION 2.a)l), above has been satisfied.

c. THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD has not been outside of the 15%

target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation cumulative during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AXIAL FLUX DIFFERENCE shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore channel at least once per 7 days when the AFD Monitor Alarm is OPERABLE, and

b. Monitoring and logging the indicated AXIAL FLUX DIFFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereaf ter, when the AXIAL FLUX DIFFERENCE Monitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFERENCE shall be assumed to exist during the interval preceding each logging.

4. 2.1. 2 The indicated AFD shall be considered outside of its 15% target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band. POWER OPERATION outside of the 15%

target band shall be accumulated on a time basis of:

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a. 0ne minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and

b. One-half minute penalty deviation for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels below 50% of RATED THERMAL POWEP.

TROJAN-UNIT 1 3/4 2-2 Amendment No. 110 l

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, REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. 51.0 vCi/ gram DOSE EQUIVALENT I-131, and

b. 5 100/E pCi/ gram.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*

a. With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time. The provisions of Specification 3.0.4 are not applicable.

b. With the specific activity of the primary coolant > 1.0 uti/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with Tavg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With the specific activity of the primary coolant > 100/E uti/ gram, be in HOT STANDBY with Tavg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1, 2, 3, 4 and 5

a. With the specific activity of the primary coolant > 1.0 uCi/ gram DOSE EQUIVALENT I-131 or > 100/E uCi/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE RFOUIREKENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

• With Tavg > 500*F.

TROJAN-UNIT 1 3/4 4-19 Amendment No. 110

(THIS PAGE INTENTIONALLY DELETED)

TROJAN-UNIT 1 3/4 4-20 Amendment No. 110

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

f. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4.7.8.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1. The fuel storage tank contains at least 200 gallons of fuel, and

2. The diesel starts from ambient conditions and operates for at least 20 minutes.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accord-ante with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM 0975-78 when checked for water, viscosity and sediment.

c. At least once per 18 months by subjecting the diesel to an inspection in' accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.8.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that:

1. The electrolyte level of each battery is above the plates, and

2. The overall battery voltage is >24 volts.

TROJAN-UNIT 1 3/4 7-25 Amendment No. 73, 39, 40, 110 l _ _

PLANT SYSTEMS 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS

• LIMITING CONDITION FOR OPERATION 3.7.11 The structural adequacy of the through-wall bolts used to tie rein-forced concrete and steel plate to the Control Building west and east walls shall be maintained at a level consistent with the acceptance criteria in Specification 4.7.11.1.

APPLICABILITY: AT ALL TIMES ACTION:

a. With the structural adequacy of the bolts not conforming to the above requirements, restore the structural adequacy of the bolts to within the limits within 14 days.

b. If the structural adequacy of the bolts does not conform to the above requirements, prepare and submit a special report pursuant to Specification 6.9.2 within the next 90 days outlining the cause of the degradation and the actions taken to restore the structural adequacy of the bolts.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.1 The structural adequacy of the through-wall bolts used to tie reinforced concrete and steel plate to the Control Building west and east walls shall be demonstrated at the end of 6 months and 1, 3 and 5 years af ter initial tensioning and at 5-year intervals thereaf ter. Structural adequacy of the bolts shall be demonstrated by:

a. Demonstrating that each bolt in a random and representative sample of not less than 25 percent of the total number of bolts has a tension equal to or greater than 80 percent of the initial bolt tension. If the tension in any bolt is below E0 percent of the initial bolt tension, tne tension in two adjacent bolts shall be measured. If either of these bolts is found to have less than 80 percent of the initial bolt tension, then all bolts shall be tested. All bolts found to have less than 80 percent of the initial bolt tension sha'11 Le retensioned to the original installation tension value.

• This Technical Specification shall become effective upon initial tensioning of the connection bolts.

TROJAN-UNIT 1 3/4 7-38 AmendmentNo.#7,65,97,797, 110 l

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. . . . . . . . _ . . .e .a 5 5 y,i1 5-3 Amendrent !;o. 7f, /J, 110

DESIGN FEATURES

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650*F, except for the pressurizer which is 680*F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,900 100 cubic feet at a nominal Tavg of 584.7'F.

5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The fuel storage racks for new fuel are designed and shall be maintained with a nominal 21-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Keft of 50.95 with the storage pit filled with unborated water, and with new fuel containing not more than 44.3 grams of U-235 per axial centimeter of active fuel assembly (3.5 wt% enrichment). The criticality analysis includes a conservative allowance for uncertainties as described in Section 4.3.2.7 of the FSAR, as amended through Amendment 26.

5.6.1.2 The storage racks for spent fuel are designed and shall be main-tained with a nominal 10.5-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Keff of 50.95 with the storage pool filled with unborated water and with new fuel containing not more than 57.0 grams of U-235 per axial centimeter of active fuel assembly (4.5 wt% enrichment). The criticality analysis includes a con-servative allowance for uncertainties as described in Section 3.1 of PGE-1037.

TROJAN-UNIT 1 5-5 Amendment No. 25, 3#, E , 110