ML20057F849
| ML20057F849 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/12/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F843 | List: |
| References | |
| GL-86-10, GL-88-12, NUDOCS 9310190237 | |
| Download: ML20057F849 (13) | |
Text
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'EE UNITED STATES S
NUCLEAR REGULATORY COMMISSION 1,, v,/
WASHINGTON, D.C. 20555-0001 NORTHEAST NUCLEAR ENERGY COMPANY i
DOCKET NO. 50-245 MILLSTONE NVCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company (the licensee), dated April 16, 1993, as supplemented June 23, 1993, complies 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 requirements have been satisfied.
9310190237 931012 PDR ADDCK 05000245 P
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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. DPR-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, are hereby incorporated in the license.-
The licensee shall operate the facility in accordance with the t
Technical Specifications.
3.
This license amendment is effective as of the date of issusnce, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
I M-o
. Stolz, Directo Pr ject Directorate I-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
[
Changes to the Technical Specifications l
Date of Issuance: October 12,.1993 I
i ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-21 i
DOCKET NO. 50-245 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert iii iii 1-1 1-1 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4
'l 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12-12 3/4 12-13 3/4 12-14 3/4 12-15 3/4 12-16 3/4 12-17 B 3/4 12-1 B 3/4 12-1 6-2 6-2 6-4 6-4 6-5 6-5 6-6 6-6 6-8 6-8 6-19 6-19 i
i t
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Surveillance Pace No.
3.11 POWER DISTRIBUTION L1 HITS 4.11 3/4 11-1 A. Average Planar Linear Heat Generation Rate (APLHGR)................... A..... 3/4 11-1 B. Linear Heat Generation Rate (LHGR)........... B..... 3/4 11-2 C.' Minimum Critical Power Ratio (MCPR).......... C..... 3/4 11-3 3.12 DELETED 3/4 12-1 i
3.13 INSERVICE INSPECTION 4.13 3/4 13-1 3.14 PLANT SYSTEMS 4.14 3/4 14-1 5.0 DESIGN FEATURES 5-1 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility.................................
6-1 6.2 Organization...................................
6-1 6.3 Facility Staff Qualifications.................. 6-2 6.4 Training.......................................
6-5 l
6.5 Review and Audit............................... 6-5 6.6 Reportabl e Event Action........................
6-14 6.7 Safety Limit Violation.........................
6-14 6.8 Procedures.....................................
6-15 6.9 Reporting Requirements......................... 6-16 6.10 Record Retenti on...............................
6-20 6.11 Radiation Protection Program...................
6-21 6.12 High Radiation Area............................
6-21 6.13 Systems Integrity..............................
6-22 6.14 Iodine Monitorir.g..............................
6-22 6.15 Radiological Effluent Monitoring and Offsite Dose Calcul ation Manual...........
6 t 6.16 Radioactive Waste Treatment....................
6-24 6.17 Postaccident Sampling / Sampling and Analysis of Pl an t E f fl u e r t s................................
6 - 2 4 i
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Millstone Unit 1 iii Amendment Nos. J, /J. JE, E!,
cons JE,65, 1
- l 1
1.0 DEFINITIONS i
The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the Specifications may be achieved.
l A.
Deleted B.
Alteration of the Reactor Core t
The act of moving any component in the region above the core support plate, below the upper grid and within the shroud with the exception of normal control rod motion.
C.
Hot Standby HOT STANDBY means operation with the reactor critical, system pressure less than 600 psig, and the main steam isolation valves closed.
D.
Immediate i
IMMEDIATE means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
E.
Instrument Calibration An INSTRUMENT CALIBRATION means the adjustment of an instrument signal output so tFat it corresponds, within acceptable range, accuracy and response time, to a known value(s) of the parameter which the instrument monitors. Calibration shall encompass the entire instrument including actuation, alarm or trip.
F.
Instrument Functional Test An INSTRUMENT FUNCTIONAL TEST means the injection of a simulated signal into the instrument primary sensor to verify the proper instrument channel response, alarm, and/or initiating action.
G.
Instrument Check An INSTRUMENT CHECK is qualitative determination of operability by observation of behavior during operation. This determinatica shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
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Millstone Unit !
I-I Amendment No.65, 0047 i
+
LIMITING CONDITION FOR OPERATION 3.12 and 4.12 These sections have been intentionally deleted per the guidance provided in Generic Letters 86-10 and 88-12.
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Millstone Unit 1 3/4 12-1 Amendment No. 65, 0088
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3.12 and 4.12 BASES These Sections have been intentionally delated per the guidance provided in Generic Letters 86-10 and 88-12.
P i
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Millstone Unit 1 B 3/4 12-1 Amendment No. 65, ooss
n.
ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued) d.
An individual qualified in radiation protection procedures shall be ca site when fuel is in the reactor.
(Table 6.2-1) e.
ALL CORE '4LTERATIONS after the initial fuel loading shall be directly,upervised by either a licensed Senior Reactor Opera-tor or senior Reactor Operator Limited to Fuel Handling who has no othur concurrent responsibilities during this operation.
f.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).
6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:
a.
The Health Physics Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, b.
The Shift Technical Advisor (STA) who shall meet the requirements of Specification 6.3.1.b.1 or 6.3.1.b.2.
I 1.
Dual-role individual: Must hold a senior reactor operator's license at Millstone Unit No.1, meet the STA training criteria of NUREG-0737, Item I.A.I.1, and meet one of the following educational alternatives:
a.
Bachelor's degree in engineering from an accredited l
institution; b.
Professional Engineer's license obtained by the successful completion of the PE examination; l
c.
Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences; d.
Bachelor's degree in a physical science from an accredited institution, including course work in the physical, mathematical, or engineering sciences; Millstone Unit 1 6-2 Amendment No. //, JJ, EE, 65, 0090
TABLE 6.2-1(5)
MINIMUM SHIFT-CREW COMPOSITION (2) i MODES APPLICABLE)
I4)
LICENSE CATEGORY 1,27: 3" 4&S II)
Senior Reactor Operator 2
I Reactor Operator 2
1 Non-Licensed Operator 2
1 Shift Technical Advisor 1(6)
None Required (1) Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling individual supervision CORE ALTERATIONS after the initial fuel loading.
(2) The above shift crew composition and the qualified health physics technicien of Section 6.2.2 may be less than the minimum requirements for l
a period of s-te not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided expeditious actions are taken to fill the required positions.
(3) Reactor Mode Switch Position is in RUN (any average coolant temperature)
STARTUP/ HOT STAhDBY (any average coolant temperature), and HOT SHUT 00WN (average coolant temperature greater than 212*F), respectively.
(4) Reactor Mode Switch Position is in SHUTDOWN (average coolant temperature less than 212*F) and REFUELING (average coolant temperature less than 212*F), respectively.
(5) Requirements for minimum number of licensed operators on shift during operation in modes other than cold shutdown or refueling are contained in 10 CFR 50.54(m).
(6) The Shift Technical Advisor position can be filled by either of the two Senior Reactor Operators (a dual-role individual), if he meets the
[
requirements of Specification 6.3.1.b.l.
Millstone Unit 1 6-4 Amendment No. 77, S,65, 0091
q-i ADMI.,ISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Station Director and shall meet or exceed the requirements and i
recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part i
55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.
I 6.5 REVIEh' AND AUDIT j
6.5.1 Plant Operations Review Committee (PORC)
Function 6.5.1.1 The PORC shall function to advise the Nuclear Unit Director on all matters related to nuclear safety.
Composition j
6.5.1.2 The PORC shall be composed of the:
Chairperson:
Nuclear Unit Director Vice Chairperson & Member:
Operations Manager Member:
Maintenance Manager Member:
Instrument and Controls Manager Member:
Reactor Engineer Member:
Radiation Protection Supervisor or Chemistry Supervisor Member:
Engineering Manager Member:
Staff Engineer Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairperson to serve on a temporary basis; however, no more than two alternates shall participate in PORC activities at any one time.
i Millstone Unit 1 6-5 Amendment No. EE, 65, 0091 l
6 ADMINISTRATIVE CONTROLS Meetina Frecuency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.
Ouorum 6.5.1.5 A quorum of the PORC shall consist of the Chairperson, or Vice Chairperson, or Nuclear Station Director and four members including alternates.
Resoonsibilities t
6.5.1.6 The PORC shall be responsible for:
Review of 1) all procedures, except common site procedures, a.
required by Specification 6.8 and changes thereto, 2) any other proposed procedures, or changes thereto, as determined by the Nuclear Unit Director to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to Sections 1.0 - 5.0 of these c.
Technical Specifications.
j d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
and preparation and forwarding of a report covering evaluation and recommendations to prevent recurrence to the Executive Vice President-Nuclear and to the Chairperson of the Nuclear Review Board.
f.
Review of all REPORTABLE EVENTS.
g.
Review of facility operations to detect potential safety hazards.
h.
Performance of special reviews and investigations and reports thereon as requested by the Chairperson of the Nuclear Review Board.
i.
Render determinations in writing if any item considered under 6.5.1.6(a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination, j.
Review of the unit-specific Fire Protection Program and implementing procedures.
Millstone Unit 1 6-6 Amendment No. J, EE, 65, 0091 i
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ADMINISTRATIVE CONTROLS Meetino Freouency i
6.5.2.4 The SORC shall meet at least once per six months and as convened by i
the SORC Chairperson.
1
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Ouorum 6.5.2.5 A quorum of the SORC shall consist of the Chairperson or Vice i
Chairperson and five members including alternates.
Responsibilities 6.5.2.6 The SORC shall be responsible for:
a.
Review of 1) all common site procedures required by Specifi-cation 6.8 and changes thereto, 2) any other proposed
)
procedures or changes thereto as determined by the Nuclear Station Director to affect site nuclear safety.
b.
Review of all propo:ed changes to Section 6.0, " Administrative Controls", of these Technical Specifications.
c.
Performance of special reviews and investigations and reports as requested by the Chairperson of the Site Nuclear Review Board.
t d.
Review of the Plant Security Plan and implementing procedures and shall submit changes to the Chairperson of the Site Nuclear Review Board.
e.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairperson of the Site Nuclear Review Board.
f.
Review of all common site proposed tests and experiments that affect nuclear safety.
g.
Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.
h.
Render determinations in writing, or meeting minutes if any item considered under 6.5.2.6(a) through (g) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question or requires a significant hazards consideration determination.
i.
Review of the common site Fire Protection Program and implementing procedures.
Authority l
6.5.2.7 The SORC shall:
a.
Recommend to the Nuclear Station Director written approval or disapproval, in meeting minutes, of items considered under 6.5.2.6(a) through (g) above.
Millstone Unit 1 6-8 Amendment No. S, 65.
0091 l
}
ag ADMINISTRATIVE CONTR0lS Special Reoorts (Cont.)
b.
Primary Containment Leak Rate Test
- Results, Specifica-tion 4.7.A.3.
c.
Materials Radiation Surveillance Specimen Examination and Results, Specification 4.6.B.3.
d.
Radiological Effluent Reports required by Specifications in 3.8.C.2, 3.8.D.2, 3.8.D.3, and 3.8.D.4.
e.
High Range Stack Monitor Inoperability per Specification l
3.8.D.7.
f.
Containment High-Range Radiation
- Monitors, Specificaticn l
i 3.7.A.7.
i l
1 Millstone Unit 1 6-19 Amendment No. J, 77, 29, EE, E/, EE,65, 0"3
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