ML20141N656

Amend 83 to License DPR-6,revising Tech Specs to Incorporate Name Change & Revised Staff Organization Chart & to Correct Typo

ML20141N656
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/10/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141N653	List: ML20141N652 ML20141N656 ML20141N657
References
NUDOCS 8603170456
Download: ML20141N656 (11)

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/ \, UNITED STATES

[ -g NUCLEAR REGULATORY COMMISSION 5

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J CONS 11MERS POWER COPPANY DOCKET NO. 50-155 RIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. DPR-6

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

A. The applications for amendment by Consumers Power Company (the licensee) dated August 5,1985, and November 1,1984, as supplemented May 16, 1985, and revised Octt,ber 9, 1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis'sion'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 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 compli-ance with the Commission'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 apolicable requirements have been satisfied.

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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 Paragraphs 2.C.(2) of Facility Operating License No. DPR6 are hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 83, 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 is.v.ince.

FOR THE NUCLEAR REGULATORY t ISSION qA./u <( s John A. Zwolinski, Director RWR ro.iect Directorate #1 Divis on of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 10,1986 i

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e ATTACHMENT TO LICENSE AMENDMENT N0.83 FACILITY OPERATING LICENSE N0. DPR-6

' DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified-below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 6-5 6-5 10-2 10-2 10-5 ~10-5 10-7 10-7 10-22 10-22 10-24 10-24 11-1 11-1 12-4 12-4

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L 6.1.2.1 Start-up Channels - Channels 6 and 7 shall provide logarithmic neutron flux level and period information from source level to five deegdes aboye source level, without moving detectors (approximately 10' to 10" : cf rated power). The principal components in each channel shall be a neutron detector, high-voltage power supFly. I

current pulse arplifier, a five decade los count rate seter with

low-level period amplifier, log count rate indicator, and los count rate recorder. Cas-filled Boron-10 lined proportional counters with a sensitivity of approximately 12 counts /nv shall be used as detectors. l  !

Provisions shall be made for remotely positioning the detectors. By moving the detectors away from the midplane of the core, their effective range may be extended several decades. A short period on either channel shall be annunciated in the control room. l 6.1.2.2 IntermediateRangeChannels-Channels 4and5providelogarithage -

r neutron flux level and period information from approximately 10 1 to rated power for the 84-bundle core. The principal components in each channel shall be a sautron detector, dual high-voltage power supply.

Log-N and period ac.plifier. Log-N indicator, period indicator. and j Log-N recorder. Thedetectorsshallbeganascompensatejgion l chambers with a design sensitivity of at least 2.2 x 10 amperes /nv.  ;

6.1.2.3 powerRangeChannels-Channels 1.2and3shallprov{delinear

! neutron flux level information frez approximately 10 1 to 125% rated power for the 84 fuel bundle core. The principal component in each I channel shall be a neutron detector, dual power supply, picosameter  !

with console range switch and power level indicator, and power level i

recorder. The detectors shall be gamma co a design sensitivity of at least 2.2 x 10-9gensatedesperes/nv. ion The chambers with  :

. amplifier output shall be connected to the reactor safety system.

6.1.2.4 In-Core Flux Monitors - In-core flux monitors shall be used to l

evaluate predicted power distributions and detect power oscillations or deviations fros expected power distributions in time for the operator to take corrective action to avoid exceeding local heat flux limits.

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6-5 Change No. 3. 7 Amendment No. 46. 83

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ADP.1NISTkATIVE CONTROLS l

3 Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related operation functions; te, senior reactor operators, reactor operators, auxiliary operators, health ohysicists and key maintenance personnel.

Adequate shif t coverage shall be usantained without routive heavy use of overtime. However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:

(1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

(2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

(3) A break, including shift turnover time, of at least eight hours should be allowed after continuous work periods of Ib hours duration.

(4) Except during extended shutdown periods, the use of overtime-should be considered on an individual basis and not for the

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entire staff on a shift.

Any deviation from the,above guidelines shall be authorized by the Plant Superintendent or his alternate (Production and Performance or Engineering and Maintenance Superintendents), or higher levels of Management, in accordance with established procedures and with documentation of the basis for granting the devist, ion.

Controls shall be included in the procedures such that individual overtise will be reviewed monthly by the Plant Superintendent or his designee to assure that excessive hours have not been assigned.

Routine deviations from the above guidelines is not authorized.

i 10-2 Amendment No. 33,83

CONSUMER 5 POWER COMPANY ~

PLANT ORGAN 12AT10N Plant Superintendent (s)

Nuclear Assurance Off-51te I

QA _ ._. Plant Review Superintendent Committee 1

QC Supe rvisor  ;

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l Chet/MP Production and Engineering & Planning and Admin Superintendent Performance Maintenance Services Superintendent Superintendent Superintendent Other Operations Supervisor Services SR0(b) .

I Shift Supervisors - SRO Figure 6.2-2 A. To support the above Plant organization. Personnel knowledgeable in the following areas identified in ANSI N18.7-1976/ ANS 3.2 will report at the discretion of r.he Plant Superintendent:

1. Nuclear Power Plant Mechanical. Electrical and Electronic Systems

2. Nuclear Engineering

3. Chemistry and Radiochemistry ,

4. Radiation Protection (Reports to Ches/MP Superintendent)

A single individual may be qualified and perform in more than one discipline.

3. The Security Force will be supervised as described in the Plant Security Plan.

C. Quality Assurance / Control activities will be in accordance with Consumers Power Company's Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A. as revised).

(a) Responsible for the Plant Fire Protection Program taplementation.

1 (b)Etther the Production tad Performance Superintendent er the Operatione Supervisor will hold an SR0 and meet the other requirements of 6.3.1 of these Technical Specifications (as applicable to Operations Manager in ANSI N18.1). .

The ladividual holding an SRO shall be responsible for directing the activities of licensed operators.

! (SRO - Seafor Reactor Operator License)

,10-5 Amendment No. ff. $3. 78.83

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.APM1h157kATIVF CONTROL' 6.3 PLANT STATT QUA11TICAT10NS 6.3.1 Each merber of the plant staff shall meet or exceed the nintrue qualificottons of ANSI N16.1-1971 for comparable positions.

6.3.2 Either the Chemistry and Health Physics Superintendent or the Chemistry and Radiation Protection Supervisor shall meet or exceed the qualifications of Regulatory cuide 1.8, September 1975.3 6.3.3 The On-call Technical Advisor (OTA) shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff l shall be maintained under the direction of the Director of Nuclear Operations Training and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CPR 55, Appendix "A."

6.4.2 The Director of Property Protection is responsible for the development, revision, approval and implementation of the Fire Brigade training program. This training shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-1975. Fire trigade training drills shall be held at least quarterly. .

6.5 REVIEV AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)

TUNCTION 6.5.1.1 The Plant Review Committee (PRC) shall function to advise the Plant '

Superintendent on all matters related to nuclear safety.

COMPOSITION i i

6.5.1.2 The PRC shall be composed of:

Chairman: Plant Superintendent or Designated Alternate Appointed by i the Plant Superintendent  !

Member: Production & Performance Superintendent Member: Planning & Admin Services Superintendent Member: Engineering & Maintenance Superintendent Member: Operations Supervisor Member: Instrument and Control Supervisor Member Reactor Engineer Member: Chemistry and Health Physics Superintendent Member: Shift Supervisor Member: Technical Engineer 3Por the purpose of this section, " Equivalent," as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following: (a) Formal schooling in science engineering, or (b) operational or technical experience / training in nuclear Power.

10-7 Amendment No. 55, 63, 83

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. o ADMINISTRATIVE CONTROLS 6.10.2 (Contd) k.- Records f or environmental qualifications which are covered under the provisions of Paragraph 6.13.

1.Recordg,yftrainingandqualificationformembersofthePlant Staff.

m. Records of reactor tests and experiments. *)

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared censistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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I") Movement of items 6.10.21 and a from section 6.10.1 increased the length ef time for which records must be retained from five years to the duration of the operating license. Since these changes in record keeping will begin on or about January 1, 1984, records of these two types created after December 31, 1978 will be retained for the duration of the operating Ifcense.

Retention for the duration of the operating license will not be required for i records of these two types created before January 1, 1979.

10-22 Amendment No. 9, Jp, 37, 53,83 l

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ADMINISTRATIVE CONTROLS i 6.12.2 (Contd)

- For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that individual area shall be barricaded, conspicuouslyposted,andaflashinglightshallbeactivatedasawarningdevice.l 10-24 Amendment No. H ,83

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. Surveillance Requirement Liettina Condition for Operation 11.4.1.4 ENERCENCY CORE COOLING SYSTEBt '

11.3.1.4 EDERCENCY CORE COOLIIIC SYSTDI i

i Applicability:

j Applicability:

Applies to periodic testing requiremente i

Applies to the operating statue of the for the emergency core cooling system.

l emergency core cooling system.

Objective:

Objective:

To asente the capability of the emergency To verify operability of the energency j core cooling systems.

core cooling system to cool reactor fuel i

!, in the event of a less of Coolant Accident.

I Specification:

Specification:

l A. Each month the following shall be performed:

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! A. h two core spray systems (original and redundant) shall be operable whenever the l

plant is in a power operation condition. Verify the operability of MO-7051. -706I.

i~ -7070. -7071, and -7066 by remote esemet j h original core spray system shall also be operable during refueling operatione. h fire actuation.

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suppreesten system can be used for routine Leak testing of the ccre spray heat purposes without declaring the core spray '

eystem inoperable provided total flow drawn eschenger.

l from the system is limited to 400 spe and Autoestic actuation of both fire pumpe.

! provided such routine uses do not exceed I

30 houre/ year. h fire suppression system can Verify that valve vpt-19 is locked er sealed I i

be used for fire fighting or for teste involving in open position.

l only flow through the fire suppreselon system relief valves without declaring the core spray

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system inoperable and without a flow and annual Verify the deluge system autoestic toelatten l

time restriction.

volve CV-4101 for the subetetten treneformer j area closes on any core sprey valve open I

N core spray recirculation system shall be signal. Verify T-handle override for valve B. CV-4101 is sealed in closed /sete poetion.

operable whenever the plant le in a power operation condition. Verify that the hooe required for bechop h core erray recirculation heat exchanger shall cooling water to the core spray recirculotten C. heet enchanger is instelled on a designated not be taken out of service during power operation l

for periode esceeding four (4) hours. h heat rock in the screenhouse.

eschenger shall be considered inoperable and out of service if tube bundle leakage esceedo 0.2 gym.

11-1 Amendment NO. 19, 15, 75, M ,83

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svRVEtt1.ANCE REQUIREMENTS

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4.7.11.1.) The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE:

a. Once per.7 days verifying the intake bay water level is abeve 570' elevation.

b. Once per 31 days by starting each pump and operating the electric driven pump for at least five minutes and the diesel pump for at least 30 minutes.

c. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTH-D975-74 with respect to viscosity, water content and sediment.

d. Once per 18 months:

1. By a systes flush and by verifying that each valve in the flow path that is not locked, sealed er otherwise secured in position is in its correct position.

2. By performing a systes functional test which includes simulated automatic actuation of the system throughout its operating sequence.

3. By verifying that each pump will develop a flow of at least 1000 spa at a systet head of 110 psi.

4. Subjecting the diesel to an inspection in accordance with procedures prepared in connection with its manufacturer's '

recommendations for the class of service.

e. Once per 3 years by performing flow tests to meet or exceed the requirements of Section 11. Chapter 5 of the Fire Protection Mandbook, 14th Edition published by National Fire Protection Association.  !

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

a. At least once per 7 days by verifying that:  ;

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

2. The overall battery voltage is k 24 volts.

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b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.

c. At least once per 18 months by verifying that:

1. The batteries and battery racks show no visual indication of physical damage or abnormal deterioration, and

2. The battery-to-battery and terminal connections are clean, tight. free of corrosion and coated with anti-corrosion material.

12-4 Amendment No. U , H 83

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