ML20108C242
| ML20108C242 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/31/1984 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20108C245 | List: |
| References | |
| NUDOCS 8411160471 | |
| Download: ML20108C242 (13) | |
Text
..
~
wrg j
UmTED ' STAT'ES NUCLEAR REGULATORY COMMISSION 3
o.
r"'
I WASHING ~. OH. D. C. 20556
- COPWONWEALTH EDISON COMPANY en-DOCKET NO. STN 50-454 i-BYRON STATION, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-23 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for license filed by Commonwealth Edison Company (licensee), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the A-t), and the Commis-sion's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made;
~ ~
B.
Construction of the Byron Station, Unit No. l (the facilitj) has been substantially completed in conformity with Construction _ Permit l
No. CPPR-130 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 1
amended, the provisions of the Act, and the regulations of the Com-1 l
mission (except as exempted from compliance in Section 2.D below);
~
D.
There is reasonable assurance:
(i)thattheactivitiesauthorized 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 Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D below);
E.
Commonwealth Edison Company is technically qualified to engage in the activities authorized by this license in accordance with the Commis-sion's regulations set forth in 10 CFR Chapter I; F.
Commonwealth Edison Company has satisfied the applicable provisions of i
10 CFR Part 140 " Financial Protection Requirements and Indemnity Agree-l ments," of the Comission's regulations; G.
The issuance of this license will not be inimical to the common defense l
and security or to the health and safety of the public; i
(
0411160471 841031 t
DR ADOCK 05000454 p
l PDR
+
,,,4_,---.--,.-.,-,s.,
-.e-,-,--e
,-~---------,y.,-
, -. _, - ~, - -
.--g
,-m,-yi r--
r rm,,%.-.,.,s
--.,c.--y
i
. H.
After weighing the environmental, economic, technical and other bene-fits of the facility against enviro,nmental and other costs and con-sidering available alternatives, the issuance of this Facility Oper-ating License No..NPF-23, subject to the conditions for protection of the environment set forth in the Environmental Protection Pian attached as Appendix B, is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and
' II The receipt, possession, and use of source, byproduct and special nu-clear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 3.0, 40 and 70.
2.
Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-23 is hereby issued to Comonwealth Edison Company (the li-censee) to read as follows:
~
A.
The license applies to the Byron Station, Unit No. 1, a pressurized water nuclear reactor and associated equipment (the facility), owned by Commonwealth Edison Coruny. The facility is located in north cen-tral Illinois within Rockvale Township, Ogle County, Illinois and is described in the licensee's " Final Safety Analysis Report", as supple-mented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses Comonwealth Edison Company:
(1)
Pursuant to Section 103 of the Act and 10 CFR Part 50 to possess, use and operate the facility at the designated.
location 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 re-quired 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 moni-toring 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 phys-ical form, for sample analysis or instrument calibration or asso-ciated 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.
C.
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 3411 megawatts thermal (100%
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% of full power (170 megawatto thermal);
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protec-tion Plan; (3) Post-Fuel-Loading Initial Test Program (Section 14, SER)
The licensee shall conduct the post-fuel-loading initial test program described in Chapter 14 of the FSAR, as amended, with-out making any major modifications unless such modifications have prior NRC approval. Major modifications are defined as:
~
(a) elimination of any safety-related test *
(b) modification of objectives, test methods, or acceptance criteria for any safety-related test
- Safety-related test are those tests which verify the design, construction, and operation of safety-related systems, structures, and equipment.
l
. (c) performance of any safety-related test at a power level different from that stated in the FSAR by more than 5 percent of rated power (d) failure to satisfactorily complete the entire initial startup test program by the time core burnup equals 120 effective full power days
.s-(e) deviation from initial test program administrative pro-cedures or quality assurance controls described in the FSAR (f) delays in test program in excess of 30 days (14 days if power level exceeds 50 percent), concurrent with power operation.
If continued power operation is desired during a delay,-the licensee shall provide justification that adequate testing has been performed and evaluated to i
demonstrate that the facility can be operated at the planned power level with reasonable assurance that the health and safety of the public will not be endangered.
(4) Seismic and Dynamic Qualification (Section 3.10, SEER #5)*
Prior to startup following the first refueling outage,.the li-censee shall completely qualify the Westinghouse 7300 Process Protection System (ESE-13), for both Nuclear Steam Supply System and Balance of Plant applications, including any hardware changes, if found necessary.
(5) Equipment Qualification (Section 3.11, SSER #5)
(a) Prior to exceeding 5% power, the licensee shall provide justification for interim operation regarding ~the issue of steam superheat caused by a postulated high energy line break outside containment.
Final resolution of this issue shall be based on the Westinghouse Owners Group findings.
(b) All electrical equipment within the scope of 10 CFR 50.49 must be environmentally qualified by November 30, 1985.
(6) fireProtectionProgram(Section9.5.1,SER,SSER#3,SSER#5)*
(a) The licensee shall maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Report for the facility through Amendment 4 and the licensee's letter dated August 20, 1984, October 11, 1984 and October 15, 1984, and as approved in the SER through Supplement 5, subject to provisions b & c below.
j
- Requires exemption; see Paragraph 2.D l
l
, (b) The licensee may make no change to the approved fire pro-tection program which would decrease the level of fire pro-tection in the plant without prior approval of the Commis-1 sios..
To make sucii a ctrange the ticens'ee must submit art application for license amendment pursuant to 10 CFR 50.90.
(c) The licensee may make changes to features of the approved
\\-
fire protection program which do not decrease the level of fire protection without prior Comission approval after such features have been installed as approved, provided
.such changes do not otherwise involve a change in a license condition or technical specification or result in an unre-viewed safety question (see 10 CFR 50.59).
However, the license shall maintain, in an auditable form, a current record of all such changes including analysis of the ef-fects of-the change on the fire protection program and shall make such records available to NRC inspectors upon request. All changes to the approved program made without prior Commission approval sha,11 be reported to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses, on an annual basis.
~
(d) Prior to exceeding 5% power operation, the licensee shall complete all modifications related to National F.ir.e Protec-tion Association Code conformance as delineated in Amend-ment 4 to the Fire Protection Report and the licensee's letters of August 20, 1984 and October 11, 1984.
(e) Prior to exceeding 5% power operation, the licensee shall complete the modifications to the carbon dioxide fire sup-pression system as described in its letter of September 19, 1934.
(f) Prior to exceeding 5% power operation, the licensee shall have an operable fire hazards panel and associated instru-mentation.
(g) Prior to exceeding 5% power operation, the licensee shall complete the analysis of spurious operation of the pressur-izer PORV's and fully implement.any necessary modifications.
(7) Control Room Human Factors (Section 18.'2, SSER #4)
J Unless the staff determines that the test results do not support the change, the licensee shall, prior to startup following the first refueling outage, move the range and volume controls for the SOURCE RANGE nuclear iristrument on Unit 1 from the nuclear instrumentation cabinet IPM07J to the main control board IPM05J.
(8) Control of Heavy Loads (Section 9.1.5, SSER #5)
Prior to startup following the first refueling outage, the' li-censee shall submit commitments necessary to implement changes and modifications required to fully satisfy (Phase-II-nine-month the guidelines of Sections 5.1.2 through 5.1.6 of NUREG-0612 response to the NRC generic letter dated December 22,1980).
.4s (9) TMI Item II.F.1, Iodine / Particulate Sampling (Section 11.5, SSER #5)
Friohtostartupfollowingthefirstrefuelingoutage,theli-censee shall demonstrate that the operating iodine / particulate sampling system will perform its intended function.
~(10) Emergency Response Capability (NUREG-0737, Supplement #1)
The licensee shall complete the emergency response capabilities as required by Attachment 2 to this license, which is incorpo-t rated into this license, j
(11) Emergency Planning (Section 13.3, SSER #4)
Prior to exceeding 5% power operation, the licensee shalli (a) Clarify its Evaluation Time Study, and amend it if neces-sary, to reflect employment-center shutdown times.
(b) Modify its Evacuation Time Study to reflect realistic time estimates under adverse weather conditions.
(c) Provide information to emergency planning officials, partic-ularly the Illinois Department of Nuclear Safety which real-t istically reflects the average generic sheltering' values of i
the structures in the Byron emergency planning zone.
3 3
(12)
Reliability of Diesel-Generators (Section 9.5.4.1, SER, SSER #5)*
Prior to startup following the first refueling outage, the con-trols and monitoring instrumentation on the local control panels shall be dynamically qualified for their location or shall be installed on a free standing floor mounted panel in such a man-ner (including the use of vibration isolation mounts as necessary) that there is reasonable assurance that any induced vibrations will not result in cyclic fatigue failure for the expected life of the instrument.
- Requires exemption; see Paragraph 2.D
. (13)
Feedwater Flow Measurement Accuracy Monitoring (Section 4.4.1, SSER #5)
Prior to completing the startup program, the licensee shall ver-ify the capability of the trending program to detect 0.1% feed-water venturi fouling, or propose a technical specification with the appropriate value of venturi fouling uncertainty and design
\\'
DNBR limits modified accordingly.
(14) Generic Letter 83-28 (Raquired Actions Based on Generic Implications of Salem ATWS Events)
The licensee shall submit responses to and implement the require-ments of Generic Letter 83-28 cn a schedule which is consistent with that given in its letters dated November 5, 1983, February 29, 1984, June 1,'1984 and October 10, 1984.
(15) Formal Federal Emergency Management Agency Finding In the event that the NRC find. that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350,-is_an indication that a major substantive problem exists in achieving or maintaining an adequate state of emer CFR Section 50.54 (s)(gency preparedness, the provisions of 10
- 2) will apply.
(16) Protection Against Postulated Breaks or Cracks In High-Energy J
and Moderate-Energy Lines (Section 3.6.2, SSER #5)*
Prior to exceeding 5% power operation, the licensee shall advise the staff of the specific uses made of NUREG-CR-2913 in " Byron 1-Confirmation of Design Adequacy for det Impingement Effects" (August 1984), by identifying each system and each of the loca-tions within that system in which it was applied. The licensee shall demonstrate that the use of NUREG-CR-2913 meets the commit-ment in FSAR Section 3.6.2 through Amendment 45 on protection against the effects of postulated pipe breaks, or provide an alternative demonstration to the NRC staff of the acceptability of its methodology.
(17) Volume Reduction System (Section 11.1 and 11.4.2, SER)
The licensee shall not process waste with the volume reduction system until the staff has completed its review of the system and issued its safety evaluation.
(18) Control Room Ventilation System (Section 6.5.1, SSER #5)*
Prior to exceeding 5% power operation, the licensee shall prepose suitable technical specifications, emergency procedures and system
- Requires exemption; see Paragraph 2.D
. modifications, as necessary, to ensure that the control room ventilation system may be used during an accident to protect operators within the criteria specified in 10 CFR 50, Appendix A,.
i General Design Criteria 19. Any required system modifications are to be operable prior to exceeding 25% power.
(19) Turbine Missiles (Section 3.5.1.3, SSER #5)
.%~
The licensee shall volumetrically inspect all three low pressure turbine rotors by every third refueling outage, until a turbine system maintenance program based on the manufacturer's calcula-tions of missile generation probabilities is approved by the staff.
(20) Operating Staff Experience Requirements (Section 13.1.2.1, SSER #5)
The licensee shall.Save a licensed senior operator on each shift who has had at least six months of hot operating experience on a similar type plant, including at least six weeks at power levels greater than 20% of full power, and who has had start-up and shutdown experience.
For those shifts where such an individual is not available on the plant staff, an advisor shall be pro-vided who has had a least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility.
Use of advisors who were licensed only at the R0 level will be evaluated on a case-by-case basis. Advisors shall be trained on plant procedures, tech-nical specifications and plant systems, and shall be examined on these topics at a le ni sufficient to assure familiarity with the plant. For each shif, the remainder of the shift crew shall be trained as to the role of the advisors.
The training of the ad-visors and remainder of the shift crew shall be completed prior to achieving criticality. Prior to achieving criticality, the licensee shall certify to the NRC the names of the advisors who have been examined and have been determined to be competent to provide advice to the operating shifts.
These advisors shall be retained until the experience levels identified in the first sentence above have been achieved.
The NRC shall be notified at least 30 days prior to the date that the licensee proposes to release the advisors from further service.
D.
The facility requires exemptions from certain requirements of Appendices A and J to 10 CFR Part 50.
These include (a) an exemption from the require-ment of Paragraph III.D.2(b)(ii) of Appendix J, the testing of containment 1
air locks at times when containment integrity is not required (Section 6.2.6 of the SER), (b) two exemptions from GDC-2 of Appendix A, the requirement that structores, systems and components important to safety be designed to withstand the effects of natural phenomena such as earthquakes (Section 3.10
[
)
1 i
-g.
and Section 3.9.3.4 of SSER #5), (c) an exemption from GDC-13 and GDC-17 of Appendix A, the requirement that instrumentation be provided to monitor variables and systems over their anticipated ranges, and the requirement that provisions be included to minimize the probability of losing electric power (Section 9.5.4.1 of SSER #5), (d) an exemption from GDC-19 of Appen-dix A, the requirement that the control room have adequate radiation pro-tection to permit access and occupancy under accident coriditions (Section
.s6s5.2 of SSER #5), (e) an exemption from GDC-3 of Appendix A, the require-ment that structures, systems and components important to safety be designed and located to minimize the probability and effect of fires (Section 9.5.1 of SSER #5), and (f) an exemption from GDC-4 of Appendix A, the requirement that structures, systems and components important to safety be appropriately protected against dynamic effects, including the effects of discharging fluids (Section 3.6.2 of SSER #5).
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 these exemptions 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.
E.
The licensee shall maintain in effect and fully _ implement all provisions of the Commission approved Physical Security Plan, Guard Training and Quali-fication Plan, and Contingency Plan, including amendments made pursuant to the authority of 10 CFR 50.54(p).
The approved plans which contain Safe-guards Information and are required to be protected against unauthorized disclosure in accordance with 10 CFR 73.21 are collectively entitled:
Commonwealth Edison Company, Byron Nuclear Power Station Physical Security Plan, Security Personnel Training and Qualification Plan *, and Safeguards Contingency Plan *, Revision 2 (May 1980), transmitted by letter dated May 2, 1980, as revised by Revision 3 (June 1980) transmitted by letter dated June 27, 1980, as revised by Revision 4 (August 1980) transmitted by let-ter of August 11, 1980, as revised by Revision 5 (January 1982) transmitted by letter of January 25, 1982, as revised by Revision 6 (April 1982) trans-mitted by letter dated April 19, 1982, as revised by Revision 7 (September 1982) transmitted by letters dated October 8 and December 22, 1982, as re-vised by Revision 8 (August 1983) transmitted by letters dated September 16, 1983 and October 28, 1983, as revised by Revision 9 (October 1983) trans-mitted by letter dated November 17, 1983, as revised by Revision 10 (January 1984) transmitted by letter dated December 30, 1983, as revised by Revisions 11 and 12 (July and August 1984) transmitted by letter dated August 29, 1984.
- The Security Personnel Training and Qualification Plan and the Safeguards Contingency Plan are Appendices to the Security Plan.
l i
' 3 F.
With the exception of 2.C(2), the licensee shall report an iolations of the requirements contained.in Sec.tJon 2.C.nf_this 1.iceas ithin 2_4 hour _s,
~
~ by ' telephone and c ~ firm by telegram, mailgram, or fosc ile transmission to the NRC Regiona Administrator, Region III, or that administrator's designee, no later han the first working day follow g the violation, with a written foll wup report within 14 days..
G.
The licensee shall r otify the Commission, as soory as possible but not later than one hour, after any accident at this facil ty which could result in an unplanned release o quantities of fission pro ucts in excess of allowable limits for normal op ration established by t Commission.
H.
The licensee shall hav and maintain fina ial protection of such type and i
in such amounts as the ommission shall quire in accordance with Section 170 of the Atomic Energy ct of 1954, a amended, to cover public liability claims.
I.
This license is effective a of the ate of issuance and shall expire at Midnight October 31, 2024.
!~
FOR E NUCLEA R TORY COMMISSION Q@,n
'n crold R. Dento, Director O
ce of Nuclear Reactor Regulation Attachments / Appendices:
p
- 1.
l'
- 2.
- 3. (Delete )
4.
Appendix A - Techni 1
Specifications ( REG-1097) 5.
Appendix B - Envi onmental e
Protection P1 Date of Issuance DCT 31 W f
- SEE PREVIOUS PAGE FOR CONCURRENCES (RETYPED 10/30 kab)
, j h
D D
hut H
ton 10/
/84 10/y /84 hD.L:DL
.,j{)LB#1:DL LB#1:DL LB#
OELD W L01shan:kab
- MRushbrook
- BJ blood
- Slewis TNovak 10/5n/84 10/26/84 10/2 4
10/29/84 10'/
/84 3i
ATTACHMENT 1 TO BYRON STATION UNIT 1 OPERATING LICENSE NPF-23 This attachment identifies certain preoperational tests and other items which must be completed to the Commission's satisfashtrand identifies the- -
required timing for their compietion.
A.
The preoperational tests and testing deficiencies identified in Attachments A and B, respectively, of the September 28, 1984, letter ifrom L. O. DelGeorge to H. R. Denton as modified by Attachment A of the October 19, 1984, letter from T. R. Tramm to H. R. Denton, shall be completed in accordance with the schedule commitments contained in those attachments except that all items shall be completed prior to exceeding 5% power.
B.
Post-fuel-loading initial test program startup procedures which have been approved by both the Station and PED shall be provided to Region III as follows:
1.
For post-core-load tests to be performed prior to the 50% power sequence, at least 10 calendar days before the start date for performance of the activity or by initial criticality, whichever occurs first.
~~
2.
For tests in the 50%, 75%, 90%, and 100% power sequences,'at least 30 calendar days before the start date of each of these sequences.
C.
Prior to exceeding 5% power, the licensee shall complete integrated testing of the Control Room (VC), Auxiliary Building (VA), Miscellaneous Electric Equipment Room (VE), and ESF Switchgear Room (VX) ventilation systems in all modes of operation to demonstrate that the Control Room envelope can be maintained at a positive 1/8 inch water gauge differential pressure with respect to adjacent areas.
D.
Prior to exceeding 5% power, the licensee shall complete confirmator measures related to qualification of energy absorbing material (EAM)y applications in pipe whip restraints as follows:
i 1.
Complete EAM testing per the technical requirements of S&L Specification 117. Amendment 4, and evaluation of the test data l
related to the resolution of field-cut EAM installations.
2.
Remove rubbing interference between compression leg and side plates for restraints MSR-33, MSR-48, and MSR-11.
3.
Submit a report to Region III describing the completion of Items 1 and 2 above.
4.
Submit a report to NRR describing:
a.
The sensitivity analysis to evaluate the effect of EAM crush strength on the function of restraint S13R-640A.
l
b.
The reconciliation of the conclusions from the Byron /Braidwood and LaSalle testing regarding reduction in EAM crush strength as a function load angularities.
c.
The results of the effective trush angle calculation for Byron.
E.
The following open and unresolved items must be resolved prior to entering the mode indicated:
il; Items Requiring Resolution Prior to Entering Mode 4 a.
Provide justification for accepting test results to resolve interferences identified on mechanical snubber connecting brackets in lieu of field inspection or modification to eliminate the interferences.
(Section3.9.3.4,SSER#5)*
b.
Address the potential problem reported pursuant to 10 CFR Part 21 relating to main steam safety valve blowdown.
2.
Items Requiring Resolution Prior to Entering Mode 2 a.
Complete the Technical Support Center (TSC) by making the ventilation system operable and by placing a copy of the approved technical specifications in the_TSC working. area.
b.
Confirm RTD time constant measurement for reactor protection time response during startup testing.
c.
Issue procedure and perform pipe vibration testing with all three charging pumps operating.
3.
Items Requiring Resolution Prior to Entering Mode 1 Review and revisc, if necessary, surveillance procedures to incorporate independent verification.
- Requires exemption; see Paragraph 2.0 2
ATTACHMENT 2 EMERGENCY RESPONSE CAPABILITIES j
The licensee shall complete the following requirements of NUREG-0737 Supple-ment #1 on the schedule noted below:
1.
Detailed Control Room Design Review (DCRDR)
The licensee shall submit the final summary report for the DCRDR by December 1, 1986.
2.
Regulatory Guide 1.97, Revision 2 Compliance The licensee shall submit by March 1,1987, a preliminary report describing how the requirements of Regulatory Guide 1.97, Revision 2 have been or will be met. The licensee shall submit by September 1, the NRC approves the DCRDR by March 1, 1987)plementation (assuming 1987, the final report and a schedule for im 3.
Upgrade Emergency Operating Procedures (EOPs)
The licensee shall submit a Procedures Generation Package within 3 months of NRC approval of Westinghouse Owners Group (WOG) Emergency Procedure Guidelines (EPG) Revision 1.
The licensee shall implement the upgraded E0Ps based on WOG E0Ps Revision I within 12 months of NRC approval of WOG EPGS Revision 1.
4.
Emergency Response Facilities The licensee shall implement the Emergency Response Facility meteoro-logical A-model by January 1, 1986 5.
Safety Parameter Display System (SPDS)
The licensee shall have SPDS operational by March 30, 1985.
-.