ML17055C067

Amend 87 to License DPR-63,changing Tech Specs to Demonstrate Feasibility of Hydrogen Water Chemistry Sys as Mitigator of Stainless Steel Piping IGSCC

ML17055C067
Person / Time
Site:	Nine Mile Point
Issue date:	07/10/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML17055C069	List: ML17055C067
References
NUDOCS 8607230121
Download: ML17055C067 (22)

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~ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 t4IAI'ARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NIICLEAR STATION, UNIT NO.

1 AMENDMENT TO FACILITY OPFPATI Nh LICENSE Amendment No. 87 License Vo. DPP-63 1.

The Nuclear Reaulatory Commission (the Commission) has found that:

A.

The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 27, 1986, complies with the standards and requirements of the'tomic Energv Act of 1954, as amended.(the Act) and the Commission's rules and regulations set forth in 10 CFR Chanter I; FI.

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'ith the Comission's regulations; D.

E.

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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended hy changes to the Technical Specifications as indicated in the attachment to this license amendment, and par aqraph 2.C.(2) of Facility Operatina License No.

DPR-63 is hereby amended to read as follows 8607230121 8607l0" L

PDR,.

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(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 87

, are hereby incorporated in the license.

The "licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGUL ORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 10, 1986 Joh A. Zwolinski, Director BWR roject Directorate ¹I Division of BWR Licensing

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ATTACfMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO.

DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached paqes.

The revised paoes are identified by the captioned amendment number and contain marqinal lines indicating the area of chanqe.

P,ENDIVE

]97 198 204 224 270 INSERT 186 192 196a 198 204 224 225a 270

LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT 3.6.1 STATION PROCESS EFFLUENTS 4.6.1 STATION PROCESS EFFLUENTS a.

Effluent release limits are described in Specification 3.6.15.

b.

The mechanical vacuum pump line shall be capable of automatic isolation by closure of the air-operated valve upstream of the pumps.

The signal to initiate isolation shall be from high radioactivity (five times normal) in the mainsteam line.*

a.

Honitoring the radioactive discharges from Nine Hi 1 e Point Unit 1 i s described in Specification'.6.15.

b.

At least once during 'each operating cycle (prior to startup), verify automatic securing and isolation of the mechanical vacuum pump.

Hithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20K rated

power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expect during the test.

The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.

The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 201. rated power, while these functions are required to be operable.

At reactor power levels below 20K rated

power, hydrogen injection shall be terminated and the injection system secured.

186 Amendment No. g, 87

TABLE 3.6.2a (cont'd)

INSTRUHENTATION THAT INITIATES SCRAH Limitin Condition for 0 eration Parameter gnimum No..

of Tripped or Operable Tri S stems Hinimum No. of Operable Instrument Channels Per Operable Tri S stem Set Point Reactor Hode Switch Position in Hhich Function Hust Be 0 erable Oo E/)

(6) Hain-Steam-Line Isolation Valve Position (7) High Radiation Hain-Steam-Line (B) Shutdown Position of Reactor Hode Switch (9) Neutron Flux (a)

IRH (i) 4(h) 3(d)

< 10 percent valve closure from full open

<5 times normal background at rated power(n)

< 96 percent of full scale (c)

(c) x x

x (k) x x

(g)

(g)

(g)

Amendment No.

31>> 87 192

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NOTES FOR TABLES 3.6.2a and 4.6.2a (cont)

(n)

Hlthin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20'L rated

power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.

The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20X rated

power, while these functions are required to be operable.

At reactor power levels below 20'L rated power, hydrogen injection shall be terminated and the injection system secured.

Amendment No.

87 196a

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TABLE 3.6.2b (cont'd)

INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limitin Cond)tion for 0 eration Parameter Hinimum No.

of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels Per Operable Tri S stem Set Point Reactor Mode Switch Position in Hhich Function Must Be 0 erable oo EA Cl.

5-nS l/l (4) High Radiation Hain Steam Line (5)

Low Reactor Pressure (6) Low-Low-Low Condenser-Vacuum (7) High Temperature Main Steam Line Tunnel 2

< 5 times normal background at rated power <<)

> 850 psig 7 in. mercury vacuum

< 200F C

X X

(a) x ~

X X

Amendment No. 37, 87 198

NOTES FOR TABLES 3.6.2b and 4.6.2b (a)

Hay be bypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi.

(b)

Hay be bypassed when necessary for containment inerting.

(c)

Hay be bypassed in the stgtdown mode whenever the reactor coolant system temperature is less than 215oF.

(d)

Only the trip circuit will be calibrated and tested at the frequencies'specified in Table 4.6.2b, the primary sensor will be calibrated and tested once per operating cycle.

(e)

Hi thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20K rated

power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.

The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20k rated power, while these functions are required to be operable.

At reactor power levels below 20X rated power hydrogen injection shall be terminated and the injection system secured.

Amendment No lA. 37.

87 204

Table 3.6.2h VACUUM PUMP ISOLATION Limitin Condition for 0 eration Parameter Minim+ No.

of Tripped or Operable Minimum No. of Operable Instrument Channels Per Operable Tri S stem Set Point Reactor Hode Switch Position in Which Function Must Be 0 erable CL Otl QJ Se c

Ql EA CK C/l CY VACUUM PUMP High Radiation Hain Steam Line

~ 5 times normal background

<a>

X X

X Amendment No. 55, 87 224

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NOTES FOR TABLES 3.6.2h and 4.6.2h (a)

Hi thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20K rated power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measuremeInts of actual radiation levels resulting from hydrogen injection.

The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20X rated power, while these functions are required to be operable.

At reactor power levels below 20X rated power hydrogen injection shall be terminated and the injection system secured.

Amendment No.

87

~ 225a

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6.12 Hi h Radiation Area (Continued) a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rates in the area have been established and personnel have been made knowledgeable of them.

c.

An individual qualified in radiation protection, with a radiation dose rate monitoring device, who is responsible for,providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified'by the Radiation Protection Supervisor or designate in the Radiation Work Permit.

6.12.2 In addition to the requirements of 6.12.1 areas accessible to personnel with radiation levels such th a major portion of the body could receive in one hour a dose greater than 1000 mrem'* shall be provided vith locked dobr's***"to prevent unauthorized entry,'and the"ha'rd keys or access provided by"tiiagnetic'eycard shall be maintained under the administrative control of the Station Shift Supervisor or designate on duty and/or the Radiation Protection Supervisor or designate.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify in accordance with site approved procedures accordingly, the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote, such as use of closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem'" that are located within large areas, such as the drywell, where no enclosure exists for purposes of locking, and ncr enclosure can be reasonably constructed around the individual areas, then that area shall be. roped off, conspicuously posted and a flashing light shall be activated as a warning device.

• by accessible passage and permanently fixed ladders

• 'easurement made at 18" from source of radioactivity

• • 'he requirement for locked doors to prevent unauthorized entry does not apply to areas which may temporarily exceed 1000 mrem/hr during the hydrogen water chemistry tests to be conducted during approximately a six-week period following startup from the spring 1986 refueling outage.

Amendment Ho.

g$, 87 270

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