NUREG-1009, License NPF-21 for Facility.Tech Specs (NUREG-1009) Encl
| ML17277B249 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/20/1983 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17277B250 | List: |
| References | |
| RTR-NUREG-1009 NUDOCS 8401170561 | |
| Download: ML17277B249 (27) | |
Text
UNITED STATES NUC~R REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 FACILITY OPERATING LICENSE License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for license filed by the Ilashington Public Power Supply System (WPPSS, also the licensee),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies
'r bodies have been duly made; B.
Construction of Washington Public Power Supply System, Nuclear Project No.
2 (the facility) has been substantially completed in conformity with Construction Permit No.
CPPR-93 and the application, as
- amended, the provisions of the Act, and the regulations of the Commission; C.
The facility will operate in conformity with the application, as
- amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D.
below);
D.
There is reasonable assurance:
(i) that the activities authorized by this operating license 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 set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below);
E.
The Washington Public Power Supply System is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The Washington Public Power Supply System has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements",
of the Commission's regulations; 840ii705bi 83i'220 PDR *DOCK 05000397 P
~
PDR G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-21, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix 8, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings regarding this facility, Facility Operating License NPF-21 is hereby issued to the Washington Public Power Supply System (the licensee) to read as follows:
A.
This license applies to the WPPSS Nuclear Project No.
2 (WNP-2),
a boiling water nuclear reactor and associated equipment, owned by the Washington Public Power.Supply System.
The facility is located on Hanford Reservation in Bento'n County near Richland, Washington, and is described in the licensee's "Final Safety Analysis Report",
as supplemented and
- amended, and in the licensee's Environmental
- Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Washington Public Power Supply System:
(1)
Pursuant to Section 103 of the Act and 10 CFR Part 50, to
- possess, use, and operate the facility at the designated location on Hanford Reservation, Benton County, Washington, in accordance with the procedures and limitations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to
- receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to
.receive,
- possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to
- possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3323 megawatts thermal
( 1005 power) in accordance with the conditions specified herein and in Attachment 1 to this license.
The preoperational
- tests, startup tests and other items identified in Attachment 1 to this license shall be completed as specified.
Attachment 1 is hereby incorporated into this license..
Pending Commission approval,.this license is restricted to power levels not to exceed 5 percent of full power (166 megawatts thermal);
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of'hich are attached
- hereto, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan;
(3)
Initial Test Program (Section 14, SER)*
The licensee shall conduct the initial test program (set forth in Section 14 of the licensee's Final Safety Analysis Report, as amended) without making any m'odifications of this program unless such modifications are in accordance with the provisions of 10 CFR Section 50.59.
In addition, the licensee shall not make any major modifications to this program unless modifications have been identified and have received prior NRC approval.
Major modifications are defined as:
{a)
Elimination of any test identified in Section 14 of the licensee's Final Safety Analysis Report, as
- amended, as being essential; (b) hodification of test objectives, methods or acceptance criteria for any test identified in Section 14 of the licensee's Final Safety Analysis Report, as
- amended, as being essential; (c)
Performance of any test at a power level different from that described in the program; and (d)
Failure to complete any tests included in the described program (planned or scheduled) for power levels up to the authorized power level.
(4)
Seismic E ui ment gualification (Section 3.10, SSER k4 Prior to startup following the first refueling outage, the licensee shall complete seismic qualifications for all equipment approved by the NRC staff for interim operation.
(5)
E ui ment Oualification Sections 3.10. 1, 3.11.3, SSER ~4)
Prior to exceeding five (5) percent of rated power, the licensee shall provide the staff for their review and approval:
(a) assurance that all equipment listed in Appendix 38 is either environmentally qualified or provide justification for interim operation.
- The paren.hetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license contion is discussed.
(b) for all pipe-mounted safety-related equipment, provide assurance that the "g" values for the as-instal led configuration do not exceed the '" 'values established in the equipment qualification information documentation
((ID) files or provide justification for interim operation.
(6)
Ultimate Heat Sink (Section 2.4.5, SER)
Prior to startup following the first refueling outage, the licensee shall perform operational testing of the ultimate heat sink spray ponds to verify analyzed parameters of drift loss, seepage and operational capacity.
The licensee shall inform the NRC staff of scheduled testing at least 30 days in advance of such testing and shall provide the test results and conclusions for NRC review and approval.
(7)
Turbine t<issiles (Section 3.5. 1.3, SSER 84 The licensee shall submit for NRC staff approval, within three years of date of issuance of this license, a turbine system maintenance program based on the manufacturer's calculations of missile genera-'ion probabilities acceptable to the NRC staff or volumetrically
'nspect all low pressure turbine rotors at the second refueling
- outage, and at every other refueling outage thereafter until a maintenance program is approved by the NRC staff.
(8)
Fuel Coolabilit (Section 4.2.3.3 I,
SER)
Prior to startup following the first refueling outage, the licensee shall provide for NRC staff review and approval revised analyses showing the effects of high-burnup fission gas release'on loss-of-coolant accident.
(9)
Inade uate Core Coolin ICC) Instrumentation Anal sis Section
.4.
SER The licensee shall implement staff's requirements regarding additional instrumentation for detection of inadequate core cooling which may result from the staff's review of the BWR Owner's Group Reports (SLI-8211 and SLI-8218) and the licensee's plant specific evaluation report addressing the subjects.
Any required modifications shall be completed on a schedule acceptable to the NRC staff.
I
(10) Thermal-H draulic Stabilit (Section 4.4.4, SER)
Prior to startup following the first refueling outage, the licensee shall provide for NRC staff review and approval a
revi sed s tab i 1 ity anal ys is.
(11) Shield Mal 1 Deferral Section 12.3.2, SSER b4)
The licensee shall complete construction of deferred shield walls as identified in Attachment 3 to this license within one (1) year after issuance of this. operating license or prior to operation of the permanent solid radioactive waste solidification system, whichever o'ccurs first.
(12) Alternate Remote Shutdown S stem Section 7.4.2.3, SSER 81 Prior to startup following the first refueling outage, the licensee shall install, test, and have operable the alternate remote shutdown system.
(13) Post Accident Sam lin (THI Action Item II.B.3, Section 9.3.2.
- SER, SSER 4
Prior to exceeding five (5) percent of rated thermal power, the licensee shall install, test, and have operable the Post Accident Sampling System.
(14) Fire Protection Pro ram, (Section 9.5. 1,
- SER, SSER b3, SSER 84 The licensee shall maintain in effect all provisions of the approved fire protection program.
(15)
Bl/R Startu or 0 eratin Ex erience (Section 13.1.2.1 1, SER)
During the startup test program, the licensee shall have on each shift a licensed individual with previous startup or operating experience on a comparable BliR, or an advisor who meets these experience requirements.
(16)
Emer enc Res onse Ca abilit (Section 18.0,
- SER, SSERP4, THI tern
. 1 an ection 1
The licensee shall correct the design deficiencies for the control room and complete the other related emergency response capabilities as required by Attachment 2 to this license.
I' (17) 0 eration with Partial Feedwater Heatin (Section
- 15. 1, SER The licensee shall not operate with partial feedwater heating for the purpose of extending the normal fuel cycle unless acceptable justification is provided to and approved by NRC staff.
(18) Modification of Automatic Depressurization S stem Lo ic-eas>
s st or Increased Diversit for Some Event Se uences II.K.3.18, Section 6.3.5,
- SER, SSER b4 Prior to startup following the first refueling outage, the licensee shall:
(a)
Install modifications to the Automatic Depressurization System acceptable to the t<RC; (b)
Incorporate into the Plant Emergency Procedures the usage of the inhibit switch; and (c)
Provide Technical Specifications for the bypass timer setting
'nd surveillance requirements for the bypass timer and the manual inhibit switch.
(19) Relocation of En ine-Mounted Controls (Section 9.5.4. 1, SEP SSER rr Prior to startup.following the first refueling outage, the controls and monitoring instrumentation on the HPCS diesel engine skid shall be installed in a freestanding floor mounted panel separate from the engine skid.
The controls and monitoring ipstrumentation shall be located in a vibration free floor area or shall be qualified for the vibrations that will occur during engine operation.
(20)
Emer enc Diesel En ine Startin S stem Section 9.5.6,
- SER, R
n Prior to startup following the first refueling outage, air dryers shall be installed in the diesel engine air starting system.
(21) Control Room Chillers Installation (Section 9.4. 1,
- 1984, redundant, seismic Category I environmentally qualified water chillers for control room HVAC.
t
(
'I I
(22) Control S stems Failures (Sections 7.7.2:1 7.7.2.2, 7.5.2.3, SER~
SSERr'4 Prior to startup following th'e first refueling outage, the licensee shall provide to NRC staff for review and approval any analysis or modifications needed to resolve the following items.
(a) capability to attain a safe shutdown condition following the loss of any Class 1E instrument bus (b) the impact of control systems failures resulting from high energy line breaks on the transient and accident analyses (c) the impact of control systems failures due to the failure of common power sources,
- sensors, or instrument sensing lines on the transient analyses.
(23)
H drod namic Loads (Section 3.9.3. 1 SER, SSERb'4 Prior to exceeding five (5) percent of rated thermal power, the licensee shall provide for NRC staff review and approval the results of the reconcilation of the hydrodynamic loads for all the safety-related piping, equipment and their supports.
(24)
Emer enc Plannin Pro ram (Section 13.3,
- SER, SSER<4 Prior to exceeding five (5) percent of rated thermal power, function-ally specific training in emergency response duties must be provided to the remaining members of the emergency organization staff who were not included in previous emergency preparedness training specified in the minimum staffing requirements of Table B-l of NUREG-0654 (including on-shift and 30 and 60 minute augmentation capability).
(25) Offsite Emer encv Pre aredness (Section 13.3, SSER 84)
Prior to exceeding five (5) percent of rated thermal power, the licensee shall certify to the NRC that:
(1)
The distribution of tone alert radios, which are part of the alert and notification system, has been completed to residents within the plume exposure pathway Emergency Planning Zone (EPZ).
(2)
The distribution of public information brochures has been completed to the population within the plume exposure pathway EPZ.
H t
(26) Pro ress of Offsite Emer enc Pre aredness (A
endix D, SER)
In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Hanagement Agency's final rule, 44 C.F.R. Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of preparedness, the provisions of 10 C.F.R. Section 50.54(s)(2) will apply.
(27) Effluent Radiation Honitors (Section 11.5, SSER P4 Prior to July 1, 1984, the licensee shall provide the following information to the NRC staff for their review and approval:
1.
Sensitivity of the effluent monitors.
2.
Evaluation of response times of these instruments.
3.
Evaluation of the instruments per criteria set forth in Section 5.4.7 of ANSI 13. 10.
4.
Compliance with Section 5.4.9 of ANSI 13. 10 5.
Evaluation of capability to provide a calibrated electrical signal to verify circuit alignment and, if used, a commitment that they be qualified.
(28) Environmental gualifications (Section
- 3. 11,
- SER, SSER k3, SSER 84)
Prior to March 31,
- 1985, the licensee shall environmentally qualify all electrical equipment according to the provisions of 10 CFR 50.49.
(29) Protection of the Environment (FES)
Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluation or that is significantly greater than that evaluation in tht Final Environmental Statement the licensee shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities.
I Exemptions from certain requirements of Appendicies G,
H and J to 10 CFR Part 50, are described in the Safety Evaluation Report.
These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
Therefore, these exemptions are hereby granted pursuant to 10 CFR 50. 12.
With the granting of this exemption the facility will operate, to the extent authorized herein, in conformity with the application, as
- amended, the provisions of the Act, and the rules and regulations of the Commission.
The licensee shall fully implement and maintain in effect all provisions of the approved physical securi.ty, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to the authority of 10 CFR 50.54(p).
The approved plans, which contain information described in 10 CFR 73.21, are collectively
- entitled, "WNP-2 Physical Security Plan" Revision 2, dated October 25, 1981 (letter dated October 22, 1981),
and Revision 3 dated March 4, 1983; (letter dated April 14, 1983), Revision 4 dated October 12, 1983 (letter dated October 21, 1983 with supplemental letter dated November 7, 1983),
Revision 5 dated November 22, 1983, (letter dated November 28, 1983);
"WNP-2 Safeguards Contingency Plan" Revision 1 dated April 1, 1981 (letter dated i)arch 14, 1983),
and Revision 3 dated October 12, 1983 (letter dated October 21, 1983);
and "MNP-2 Training and gualification Plan" dated November 16, 1979 (letter dated November 16, 1979), Revision 1 dated June 26, 1981 (letter dated July 1, 1981),
and Revision 2 dated November 2, 1981 (letter dated October 14, 1981).
With the exception of 2.C(2) the licensee shall report any violations of the requirements contained in Section 2.C, and E of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm by telegram,
- mailgram, or facsimile transmission to the NRC Regional Administrator, Region V, or that administrator's
- designee, no later than the first working day following the violation, with a written followup report within 14 days.
The licensee shall notify the Commission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities'f fission products in excess of allowable limits for normal operation established by the Commission.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as
- amended, to cover public liability claims.
~ 1
I.
This license is effective as of the date of issuance and shall expire at Midnight on December 20, 2023.
FOR THE NUCLEAR REGULATORY COMMISSION i~S~Mlof~gg by t Attachments/Appendicies:
l.
Attachment 1
2.
Attachment 2
3.
Attachment 3
4.
Appendix A - Technical Specifications (NUREG-1009) 5.
Appendix B - Environmental Protection Plan Date of Issuance:
Opg p O
~QIEII Harold R. Denton, Director Office of Nuclear Reactor Regulation
- SEE PREVIOUS CONCURRENCES DL:LBk'2/PM
- DL:LB82/LA" RAuluck:pt
, EGHylton 12/12/83 12/12/83 NRR NRR EGCase HR ton 12/ /83 12/+83 DL:LB82/BC" OELD *
. D/L DL ASchwencer MPa<<n T Novak ssenhut 12/
1 /83 12/1 2/83 12/) t
/83 12/A@83
ATTACHMENT 1 TO l<PPSS NUCLEAR PROJECT NO.
2 P
R NG LICENS NP -21 The licensee shall complete the following requirements within the schedule noted below:
1..
Prep erational/Acce tance Tests a.
The licensee shall, prior to loading of fuel in the core, complete the System 36 preoperational testing to assure that those monitors required for fuel load fully meet the Technical Specification requirements without reliance on action statements:
b.
The licensee shall successfully complete the following preoperational/acceptance tests before exceeding 5% power:
PT 33.0-B Chemical Haste Processing PT 37.0-D Miscellaneous Radiation tlonitoring Equipment PT 40.0-A Off-Gas System AT 65.0-A Sealing Steam System AT 66.0-A Condenser Air Removal PT 69.0-A Condensate System PT 70.0-A Condensate Storage Transfer PT 71.0-A Condensate Filter Demineralizer System PT 72.0-A Reactor Feedwater Turbine and Pumps PT 72.0-8 Reactor Feedwater Controls AT 74.0-A Heater Vents and Drains AT 82.0-A Turbine Building Heating and Ventilating PT 92.0-A Off-Gas Vault HVAC AT 110.0-A Loose Parts Detection PT 201.0-A Primary Containment Integrated Leakage Rate Test AT 302.0-A Integrated Condenser In-Leakage Test c.
The licensee shall complete PT 22.0-B, Nitrogen Interting System prior to six months after initial criticality.
2.
Han ers Su
- orts, and Restraints All QI-SI and QII-SI hangers,
- supports, and restraints needing installation and/or modification will be completed prior to exceeding 5A power.
3.
Construction Com letion (Master Com letion List Schedule The licensee shall restrain fuel loading, primary system steam pressurization, exceeding 5X power, and commerical operation* by prerequisite completion of the associated categories of items in accordance with ihe schedule shown on the Project Master Completion List dated December 19, 1983.
The licensee shall not extend the completion categories for individual items on the list without prior notification and individual concurrence by a representative of the NRC Regional Office.
- Commerical operation is defined as the 100K power warranty run or July 1, 1984, whichever occurs first,
f
ATTACHMENT 2 The licensee shall complete the following requirements on the schedule noted below:
1.
Detailed Control Room Desi n Review DCRDR The licensee shall submit a program plan for DCRDR for NRC staff review within two (2) months after the issuance of this operating license and a
summary report not later than six (6) months prior to the first refuel.ing outage.
2.
Control Room Desi n
Im rovements The licensee shall correct and implement to the NRC staff's satisfaction, the following human engineering deficiencies prior to exceeding five (5) percent of rated thermal power:
A 5.17*
A 7.15 D 3.59 D 4.23 D 5.40 D 5.44 D 5.46 D 6.101 D 8.38 D 9.5 E 5.61 E 5.69 F 4.37 Inoperative System Status Panels Inoperative TDAS and GDS computer systems Multiple-meaning abbreviations, lack of abbreviation control Hard-to-operate pushbuttons on controllers Non-standard fuel-zone monitor meter scale, P-601 Identical push button/non-push button status lights, P-820 Identical push button/push button indicator lights, Rod Worth Minimizer, Rod Monitor control subpanels, P-603 Inadequate labeling, Isolation Control, P-601 Non-identical RFW meter groupings for Systems A
8 B, P-840 Inconsistent
- scales, CW Inlet Plenum Lever Indicator and Controller, P-840 Recorder poi.nters obscure scale numerals/graduation marks RPV depressurization procedures call for greater reading accuracy than is provided by pressure indicators Switch handles obscure pointers/labels, P-800 The licensee shall correct and implement to the NRC staff's satisfaction,.
the following human engineering deficiencies within four (4) months after the issuance of this operating license:
A 3.4 D 4.22 D 5.49 E 3.71 E 4.27 F 6.115 F 6.116 Audio 'alarm signal detection and intensity levels Extension 'handles for throttlable valve controls, P-820 Proper chart paper for Generator Monitor Temperature
- Recorder, P-820 Inconsistent pushbutton color coding Extension handle for RPS reset switch, P-603 Inconsistent fonts, switch escutcheon legends Inconsistent pushbutton color coding
- HED finding identification as given in NRC letter to D.
W. Mazur dated 9/20/83.
0 Attachment 2
3.
Re ulator Guide 1.97, Revision 2
Com liance (a)
The licensee shall implement ('nstallation or upgrade) requirements of R.G.
1.97 Rev.
2 with the exception of flux monitoring prior to startup following the first refueling outage.
(b)
The licensee shall implement (installation or upgrade) requirements
'of R.G.
1.97 Rev.
2 for flux monitoring prior to March 31, 1985.
4.
U qrade Emer enc 0 eratin
.Procedures EOPs)
The licensee shall provide within two(2) months after the issuance of this operating license, an addendum to the Procedures Generation Package describing the function and task analysis as identified in Supplement 1
to HUREG-0737.
5.
Emer enc Res onse Facilities The licensee shall have fully functional emergency response facilities (Technical Support Center, Operational Support Center, and Emergency Operations Facility) prior to exceeding five (5) percent of rated power.
b ~
l
ATTACHliENT 3 LIST OF SHIELD HALLS 1.
FSAR Fi ure 12.3-22 Zone H The partial height wall outside the spent resin tank room.
2.
FSAR Fi ure 12.3-26, Zone G The tube access wall to the main condenser.
3.
FSAR Fi ure 12.3-27, Zone 0 The access blockout to the spare demin-era izer cu
>c e.
5.
FSAR Fi ure 12.3-33, Zone G. Same as above for the duplicate centri-uge room.
6.
FSAR Fi ure 12.3-33 Zone F Same as above for the duplicate centri-fuge.
7.
FSAR Fi ure 12.3-34, Zone H-5/J The blockout for one of the two econ concentrators.
8.
FSAR Fiqure 12.3-32, Zone D The two block walls at the north end.
of the true oading bay.
9.
FSAR Fi ure 12.3-32, Zone E The leaded glass viewing window in the radwaste area.
A h
R l