ML20079G324
| ML20079G324 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/30/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20079G327 | List: |
| References | |
| DPR-22-A-019 NUDOCS 8401200037 | |
| Download: ML20079G324 (6) | |
Text
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NORTHERN STATES POWER COMPANY DOCKET N0. 50-263 PONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.19 License No. DPR-22 1.
The Nuclear Regulatory Commission (the Commissior.) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated September 24, 1982, complies with the standards and reauirements 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 recuirements have been satisfied.
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-22 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.19 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8401200037 831230 PDR ADOCK 05000263 P.
2 2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-
/
Domenic B. Vassallo, Chief Operating Peactors Branch #2 Division of Licensino
Attachment:
Changes to the Technical Specifications.
Date of Issuance:
December 30, 1983' 9
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a ATTACHMENT TO LICENSE AllENDMENT N0.19 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 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 area of change.
Remove Insert 244 244 24da 245 245 O
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9 6.5 Plant operating Proccitures i
Detailed uritten procedures, including the applicable check-ott ~ llst,.unt Instructions, covering areas listed lalos j
sha1l be prepa reil anel f u t loweil.
- 1bese procedutes and changes Iheae o,
except as spec 1Iled in 6.5.F sha11 he reviewed by the Opera t ion Commi t tee and approved by a memi.er of plant management designa ted by the Plant ~ flanager.
A.
Plant Opeiations l.
Integrated and system proceduren for normal sta rtup, ope r.it t on anil sins tdoun of the reactor aint all systems and components involving nuclear safety of the facill t /.
2.
Fuel hand ling opera t ions.
~
t 3.
Actions to be taken to correct specific and forescen t"St ent ial or actual malfunction of systems.or components including respouses to alarms, primaty system leak and.shnoimal reacttvity changes and inclinling follow-up acttons reynlied af ter plant protecttve system actlons have inttlated.
4.
Surveillance and testing requirements that could have an efIcet on nuclear safety.
j 5.
Implemen t ing p. ocedure:t ut the securi ty plan.
i b
6.
Impleeyenting procedures of the emergency plan, including procedures for coping with emergency conditions Involvint; poten t ial or ac te:al releases of radioactivity,
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j 7.
I mp l emen t ini; procedures of the fire protectton program.
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8.
Implement ing procedures for the Process Contral Program and offsite Done Calcul.ition flanual including l
'lua l t t y con t rol measu res.
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Drills on the procedures specified in A.3 above shall be ronducted.a, a pa r t of the ret raining program. Drills on l
the procedures specifled in A. 6 a bove. shall he conducted at least nemi.ninual ly, including a check of cocununications I
with offsite support groups.
l 6.s 244 Amendinent flo. yf,19
4 B. Radiological 1.a. A Radiation Protection Program, consistent with the requirements of 10 CFR 20, shall be developed and followed. The Radiation Protection Program shall consist of the following:
(1) A Radiation Protection Plan, which shall be a complete and concise statement of radiation protection policy and program (2) Procedures which implement the requirements of the Radiation Protection Plan l
The Radiation Protection Plan and implementing procedures, with the exception of those non-safety related procedures governing work activities exclusively applicable to or performed by health physica personnel, shall be reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager. Health physics procedures not reviewed by the Ope. rations _ Committee,shall be reviewed and app-roved by the, Superintendent, Radiation Pyqtection.
I i
b.
Par 1 graph 20.203 " Caution signs, lables, signals and controls." In lieu of the " Control device" or alarm signal required by paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a i
Radiation Work Permit and any individual or group of individuale permitted to enter such areas shall be.provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
The above procedure shall also apply to each high radiation area in which the intensity of c.
radiation is greater than 1000 mrem /hr, except that doors shall be locked or attended to
- p. event unauthorized entry into these' areas and the keys or key devices for locked doors shall be maintained under the administrative control of the Plant Manager, i
Amendment No.19 i
6.5 244a
i 2.
A program shall be impleinented to reduce leakage from systems outelde containment that would or could contain highly radioactive fluide during a serious transient or accident to es low as practleal levels. This program shall include the following Provisions establishing preventive maintenance and periodic visual inspection require-s.
ments, and b.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
A program acceptable to the Commission was described in a letter dated December 31, 1979, from L 0 Heyer HSP, to Director of Nuclear Reactor Regulation, " Lessons Learned liep t eme nt a t lon".
3.
A program shall be isiplemented which w!!! ensure the capability to accurately determine the airborne lodine concentration in essentist plant areas under accident conditions. This program shall include the followings a.
Training of personnel, b.
Procedures for monitoring, and Provisions for maintenance of. sampling and analysis equipment.
c.
A program acceptable to the Comunission was described in a letter dated Decereber 31, 1979, from L 0 Hayer. HSP, to Director of Huclear Reactor Regulation, " Lessons Learned Imptementatlon".
Amendment No. 19 6.5 245 0