ML19323C709
| ML19323C709 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png (DPR-39-A-054, DPR-39-A-54, DPR-48-A-051, DPR-48-A-51) |
| Issue date: | 04/28/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323C708 | List: |
| References | |
| NUDOCS 8005190038 | |
| Download: ML19323C709 (24) | |
Text
8005180079
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'o UNITED STATES E'
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NUCLEAR REGULATORY COMMISSION l
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 2, 1977, supplemented by letters dated February 26 and September 26, 1979, and applications dated September 28 and November 7, 1979, 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 issance 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendixes A and B, as revised throtgh Amendment No.
54, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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E 3.
The license is further amended by adding the followiag new paragraph
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2.C.(8):
- 3 2.C.(8) - The licensee shall implecent a secondary water chemistry mon-E itoring program to inhibit steam generator tube degradation. This program shall include
lH 1.
Identification of a sampling schedule for the critical parameters i;
and control points for these parameters;
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2.
Identification of the procedures used to quantify parameters that are critical to control points;
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3.
Identification of process sampling points;
)
4.
Procedure for the recording and management of data;
[E EI 5.
Procedures defining corrective actions for off.' control point chemistry conditions; and
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6.
A procedure identifying the authority responsible for the interpre-tation of the data and the sequence and timing of administrative
. events required to initiate corrective action.
L 4.
The license amcadment is effective as of the date of issuance.
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!i FOR THE N LEAR REGULATORY COMMISSION 4N A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Attachments:
Changes to the Technical Specifications Changes to Facility Operating License No. DPR-39 pgs. 5 & 6 & 6a Date of Issuance: April 28, 1980
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- o UNITED STATES
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WASHINGTON, D. C. 20555 e
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. OPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for ainendment by Commonwealth Edison Company (the licensee) dated September 2, 1977, supplemented by letters dated February 26 and September 26, 1979, and applications dated September 28 and November 7,1979, 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 wil' be conducted in compliance with the Commission's regulations; O.
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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(8) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendixes A and B, as revised through Amendment No.
51, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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L 3.
The license is further amended by adding the following new paragraph 2.C.(8):
2.C.(8) - The licensee shall implement a secondary water chemistry mon-itoring program to inhibit steam generator tube degradation.
This program shall include:
1.
Identificatio.' of a sampling schedule for the critical parameters and control points for these parameters; 2.
Identification of the procedures used to quantify parameters that are critica' to control points; 3.
Identification of process sampling points; 4.
Procedure for the recording a6d management of data; 5.
Procedures defining corrective actions for off? control point chemistry conditions; and 6.
A proccdure identifying the authority responsible for the interpre-tation of the data and the sequence and timing of administrative
. events required to initiate corrective action.
4.
The license amendment is effective as of the date of issuance.
FOR THE N EAR REGULATORY COMMISSION kM D
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Attachments:
Cha1ges to the Technict1 Specifications Changes to Facility Operating License No. DPR-48 pgs. 4, 5 & 6 & 6a Date of Issuance: April 28, 1980 l
l
ATTACHMENT TO LICENSE AMENDMENTS A 'ENDMENT NO. 54 TO FACILITY OPER TING LICENSE NO. DPR-39 AMENDMENT NO. 51 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 1.
Revise Appendix A of the Technical Specifications as follows:
Remove Pages Insert Pages 59 (Unit 2 only-)
59 (Unit 2 only) 73 73 79 79 80 80 82 82 83 83 94 94 164 164 168 168 174 174 315 315 328a 328a 2.
Replace the following pages of the Facility Operating License No. OPR-39 and DPR-48 with the attached pages as indicated.
The change area in the license is indicated by a marginal line:
Remove Pages
- Insert Pages 5 Unit 1 5 Unit 1 6 Unit 1 6 Unit 1 4 Unit 2 4 Unit 2 5 Unit 2 5 Unit 2 6 Unit 2 6 Unit 2 6a Unit 1 6a Unit 1 6a Unit 2 6a Unit 2
- These pages were retyped to include all previous amendments to the licenses.
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5-I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) This amended license is subject to the following conditions for the pro-tection of the environment:
(a) Radiological and non-radiological Technical Specifications have been established by the Regulatory staff. These Technical Specifications cover, but are not limited to, the following:
(1) An extended operational monitoring program to determine the environmental impacts of Station operation.
The program should determine the size, shape, and location of the thermal plume during different wind and weather conditions.
The program should define the effects of facility operation on the aquatic ecosystem, including data on impingement of aquatic organisms on the bar racks and traveling screens.
i
.(2) A basis for starting the deicing operation (pumping heated discharge water to the intake structure) only after there are positive indications that icing of the offshore intake struct-ure is in fact taking place.
Q) Commonwealth Edison shall develop design modifications to the condenser cooling water intake structure to reduce the effective water intake 1
velocity to less than 1 foot per second (under winter deicing opera-tions the present velocity is calculated to be over 3.7 fps; during non-winter operation it is calculated to be over 2.4 fps); or to otherwise minimize fish entrainment.
Commonwealth Edison will be prepared to install the modifications within a specified time period if excessive nunbers of juvenile or adult fish mortalities result from operation of the condenser cooling water system.
(c) If important adverse effects or tvidence of irreversible damage are detected by the monitoring programs, Commonwealth Edison will provide to the Commissior an analysis of the problem and a plan of action to be taken to eliminate or acceptably reduce the detrimental effects or damage.
1 (d) Commonwealth Edison shall perform fish population studies in the offshore control areas to provide base line population statistics for all seasons of the year.
Commonwealth Edison shall monitor the quantity and quality of fish population in there areas and shall assure that these control areas are outside the influence of the thermal plume.
Commonwealth Edison shall submit this fish popula-tion study program to the Commission for review by January 15, 1974.
Amendment No. 54 Unit 1
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(4) The licensee shall not operate the reactor at power levels above P-7 (as defined in Section 7.2 of the Zion Final Safety Analysis Report) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted and approval for less than four loop operation at power levels above P-7 has been granted j
by the Commission by amendment to this license.
(5) The licensee may proceed with and is required to complete the modifications indicated in Paragraphs 3.1.1 through 3.1.20 of the NRC's Fire Protection Safety Evaluation (SE) on the Zion Nuclear Power Station dated March 10, 1978 and supplements thereto.
These modifications shall be completed as specified in Table 3.1 of Supplement No. 1 or in subsequent supplements to that SE.
In addition, the licensee shall submit the additional informa-1 tion identified in Table 3.2 of the above cited SE in accordance with the i
schedule contained therein.
In the event these dates for submittal cannot be net, the licensee shall submit a report explaining the circum-i stances, +.ogether with a revised schedule.
i (6) The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan documents, withheld from'public disclosure pursu-ant to 10 CFR 2.790(d), collectively titled " Zion Station Dr.it Nos.1 and 2 Physical Security Plan," dated November 18, 1977 as revised May 26 and July 25,1978."
(7) Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the applicatior. dated April 13, 1978, as supplemented October 24, Novem-ber 8 and 29, 1978, January 24 and 26, February 23, March 7 and 19,1979.
(a) Fuel stored in the spent fuel pool shall have a U-235 loading less than or equal to 40.6 grams per axial centimeter.
(b) No loads heavier than the wright of a single spent fuel assembly plus the tool for moving that assembly shall be carried over fuel stored in the spent fuel pool.
The spent fuel handling tool, tha burnable poison tool, the rod cluster control changing fixture and the thimble plug shall not be carried at heights greater than two feet over fuel stored in the spent fuel pool.
(c) The NRC shall be notified in advance should it become necessary to handle heavy loads in the vicinity of the spent fuel storage pool.
(d) Upon completion of the modification a corrosion surveillance program for the racks shall be implemented and kept in force to insure that any loss of neutron absorber material and/or swelling of the storage tubes is detected.
Amendment No. 54 Unit 1
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b
- 6a -
(e) In situ neutron attenuation tests shall be performed to verity that tubes and racks contain a sufficient number of Boral plates such D
that K-effective will not be greater than 0.95 when the spent fuel is in place.
Results of these tests shall be reported to the NRC within 30 days after completion of tha modification.
(8) The licensee shall implement a secondary water chemistry monitoring
]
program to inhibit steam generator tube degradation.
This program shall include:
(a) Identification of a sampling schedule for the critical parameters and control points for these parameters; (b) Identification of the procedures used to quantify parameters that are critical to control points; (c) Identification of process sampling points; (d) procedure for the recording and management of data; (e) Procedures defining corrective actions for off contral point chem-istry conditions; and (f) A procedure identifying the authority responsible for the interpre-tation of the data and the sequence and timing cf administrative events required to initiate corrective action.
Amendment No. 54 Unit 1
. C.
This license shall be deemed to contain and is subject to the condi-tions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is sub-ject to all applicable provisions of the Act and to the rules, regu-lations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1) Maximum Power Level Commonwealth Edison Company is authorized to operate the Zion Nuclear Power Station Unit No. 2 at steady state reactor core power levels not to exceed 3250 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 51, are hereby incorporated in the licease.
The licensee shall operate the facility in accord-ance with the Technical Specifications.
(3) This license is subject to the following conditions for the protection of the environment:
(a) Radiological and non-radiological Technical Specifications have been established by the Regulatory staff. These Technical Specifications cover, but are not limited to, the following-(1) An extended operational monitoring program to determine the environmental impacts of Station operation.
The program should determine the size, shape, and location of the thermal plume during different wind and weather i,
conditions. The program should define the effects of facility operation on the aquatic ecosystem, including data on impingement of aquatic orga' isms on the bar n
racks and traveling screens.
(2) A basis for starting the deicing operation (pumping heated discharge water to the intake structure) only after there are positive indications that icing of the offshore intake structure is in fact taking place.
(b) Commonwealth Edison shall develop design modifications to the condenser cooling water intake structure to reduce the effective water intake velocity to less than 1 foot per second (under winter deicing operations the present velocity is calculated to be over 3.7 fps; during non-winter operation it is calculated to be over 2.4 fps); or Amendment No. 51 Unit 2
-S-l to otherwise minimize fish entrainment.
Commonwealth Edison will be prepared to install the modifications within a specified time period of excessive numbers of juvenile or adult fish mortalities result from operation of the condenser cooling water system.
(c) If important adverse effects or evidence of 'rreversible i
damage are detected by the monitoring programs, Commonwealth Edison will provide to the Commission an analysis of the i
problem and a plan of action to be taken to eliminate or acceptably reduce the detrimental effects of damage.
(d) Commonwealth Edison shall perform fish population studies in the offshore control areas to provide base line popula-1 tion statistics for all seasons of the year.
Commonwealth Edison shall monitor the quantity and quality of fish population in these areas and shall assure that thes control areas are outside the influence of the thermal plume.
Commonwealth Edison shall submit this fish popula-tion study program to the Commission for review by January 15, 1974.
(4) The licensee shall not operate the reactor at power levels above P-7 (as defined in Section 7.2 of the Zion Final Safety Analysis Report) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment to this license.
(5) The licenser may proceed with and is required to complete the modifications indicated in Paragraphs 3.1.1 through 3.1.20 of the NRC's Fire Protection Safety Evaluation (SE) on the Zion Nuclear Power Station dated March 10, 1978 and supplements thereto.
these modifications shall be completed as specified in' Table 3.1 of Supplement No. 1 or in subsequent supplements to that SE.
In addition, the licensee shall submit the addi-tional information identified in Table 3.2 of the above cited SE in accordance with the schedule contained therein.
In the event these dates for submittal cannot be met, the licensee shall submit a report explaining the circumstances, together with a revised schedule.
j (6) The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved security plan documents, withheld from public disclosure pursuant to 10 CFR 2.790(d),
collectively titled " Zion Station Unit Nos. 1 and 2 Physical Security Plan," dated November 18, 1977 as revised May 26 and July 25, 1978.
Amendment No. 51 Unit 2
. (7) Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated April 13, 1978, as supple-mented October 24, November 8 and 29, 1978, January 24 and 26, February 23, March 7 and March 19, 1979.
(a) Fuel stored in the spent fuel pool shall have a U-235 loading less than or equal to 40.6 grams per axial centimeter.
(b) No loads heavier than the wright of a single spent fuel assembly plus the tool for moving that assembly shall be carried over fuel stored.in the spent fuel pool.
The spent fuel handling tool, the burnable poison tool, the rod cluster control changing fixture and the thimble plug shall not be carried at heights greater than two feet over fuel stored in the spent fuel pool.'
(c) The NRC shall be notified in advance should it become necessary to handle heavy loads in the vicinity of the spent fuel storage pool.
(d) Upon completion of the modification a corrosion surveillance program for the racks shall be implemented and kept in force to insure that any loss of neutron absorber material and/or swelling of the storage tubes is detected.
(e) In situ neutron attenuation tests shall be performed to verify that tubes and racks contain a sufficient number of Boral plates such that K effective will not be greater than 0.95 when the spent fuel is in place.
Results of these tests shall be reported to the NRC within 30 days after completion of the modification.
(8) The licensee shall implement a secondary water chemistry monitor-ing program to inhibit steam generator tube degradation.
This program shall include:
(a) Identification of a sampling schedule for the critical parameters and control points for these parameters; (b) Identification of the procedures used to quantify para-meters that are critical to control points; (c) Identification of process sampling points; (d) Procedure for the recording and management of data; Amendment No. 51 Unit 2
- 6a -
(e) Procedures defining corrective actions for off control point chemistry conditions; and (f) A procedure !dentifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.
3.
The conditions imposed by the Atomic Safety and Licensing Board relative to the fuel densification phenomenon are being satisfied by the inclusion of the power level restrictions of Figure 3.2-9b of the T hnical Specifications, as amended.
4.
The conditions imposed by the Atomic Safety and Licensing Board and the Atomic Safety and Licensing Appeal Board relative to the Industrial Security Pla.2 are set forth in Appendix C, as revised by issued changes through Change No. 1, of this amended license, and are incorporated herein by reference. Appendix C is being given restricted distribution.
5.
This license is issued without prejudice to subsequent licensing actior which may be taken by the Commission.
6.
This license is effective as of the date of issuance and shall expire at midnight on December 26, 2008.
FOR THE ATOMIC ENERGY COMMISSION Original signed by Roger S. Boyd A. Giambuso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
Nov. 14, 1973 Amendment No. 51 Unit 2
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l Figure 3.2-4 CONTROL ROD INSERTION LIMITS FOUR-LOOP OPERATION Zion Unit 2 i
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20 40 60 80 100 POWER LEVEL (% OF RATED POWER)
Amendment No. 51, Unit 2 59 -
I LIF:ITING' CONDITION FOR OPERATION SURVEILLANCE REQUIREF2NT l
30 3 Reactor Coolant System '(per unit) 4.3 Reactor Coolant System (per unit)
Applicability Applicability Applies to a Reactor Coolant System Applies to the monitoring of Reactor operational status, heatup and cooldown, Coolant System surveillance.
leakage, structural integrity, chemistry and radio-chemistry.
Objective Objective To assure the. integrity and safe operation To establish surveillance Tequirements for a of a Reactor Coolant System.
Specification (per unit)
Specification (per unit) 4 1.
Operational Components 1.
Operational Compone'nts A.
Reactor Coolant Pumps A.
Reactor Coolant. Pumps 1.
The reactor coolant pumps shall 1.
Not Applicable be operational as specified in sections 3.2.1.D.5, 3.2.1.D.6, 2.1. 2.B and Table 3.1-1.
Three 3
loop operation is specified in sections 3.2.1.D.6, 2.1.2.B and 3
Table 3.1-1. (See 3. 3.2.G for low RCS temperature operation.)
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Amendment No. 54, Unit 1 73 Amendment No. 51, l' nit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3 2.
Pressurization and System Integrity 4.3 2.
Pressurization and System Integrity A.
Ileatup and Cooldown A.
Not Applicable The Reactor Coolant System temperature and pressure (with the exception of the pressurizer) shall be limited in accordance with the limit lines shown in Figures 3.3.2-1 and 3.3.2-2 during heatup, cooldown and inservice leak and hydrostatic testing.
1.
Allowable combinations of pressure and temperature for specified temperature I
change rates are below and of the right of the limit lines shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation.
2.
Figures 3.3.2-1 and 3.3.2-2 define limits to assure prevention of non-ductile failure only.
For normal operation other inherent plant characteristics, e.g.,
pump heat addition and pressurizer heater capacity may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges.
3.
The Reactor Coolant System shall be limited to a maximum temperature change of 100F/hr during inservice Amendment No. 54, Unit 1 Amendment No. 51, Unit 2 79
LIMITIt;d CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.2.
A3. (Continued) leak and hydrostatic testing operations above the heatup and cooldcwn lisait curves.
B.
The limit lines shown in Figures 3.3.2-1 and 3.3.2-2 shall be recalculated periodically as required, based on results f rom the material surveillance program.
C.
The secondary side of the steam generator must be pressurized above 200 psig if the temgerature of the vessel is below 70 F.
D.
The pressurizer heatup rate shall not 0
exceed 100 F/hr and the pressurizer 0
cooldown rate not exceed 200 F/hr.
The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 3200F.
E.
Hydrostatic Testing 1.
System inservice leak and hydrotests shall be performed in accordance with the require-ments of ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, up to and including Summer 1975 Addendum.
Amendment No. 54, Unit 1 Amendment No. 51, Unit 2 80
LIMITING CONDITION FOR CPERATION SURVEILLANCE REQUIfU: RENT 3.3.2.G I.ow Temperature overpressure Protection 4.3.2.G Low Temperature Overpressure Protection 1.
When the temperature of the reactor 1.
Surveillance a.id testing of the low coolant system (HCS) is below 250 P temperature overpressure protection and the reactor head is installed:
shall be performed as follows:
a.
Two power operated relief valves a.
Within 31 days prior to entering a (PORVa) with a lift setting of condition in which the PORVs are 435 psig shalI be operable except required operable and at least as specified in 3.3.2.G.I.a.1 and once per 31 days while the PORVs 3.3.2.G.I.a.2 or are required operable, a channel functional test (including valve k
1.
One I ORV may be inoperable for operation) shall be performed on no more than 7 days.
each PORV. A channel calibration shall be perforned at least once per 18 months.
2.
If one PORV is inoperable for 1.
Not applicable more than 7 days or if two PORVs are inoperable, the 2.
Same as 4. 3. 2.G. I.c pressurizer level shall be lower than 25% and the pressurizer pressure shall be lower than 100 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; the pressurizer shall remain in these conditions until both PORVs Ere restored to the operable.=tatus.
.).
One power operated relief valve shall b.
Not applicable.
be open or c.
The pressurizer level shall be below c.
The pressurizer level shall be 25% and the pressurizer pressure verified to be below 25% shiftly shall be below 100 psig.
and the pressurizer pressure shall be verified to be below 100 psig shiftly.
82 Amendment No. 54, Unit 1 Amendment No. 51, Unit 2
LIMITItJG COr1DITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.2.G (Continued) 4.3.2 G (Continued) 2.
Only one of the three charging pumps, 2.
Two charging pumps, both safety no safety injection pumps, and no injection pumps, and all accumulators shall be operable wgen accumulators shall be verified the RCS temperature is below 250 P inoperable before bringing the and the reactor head is installed.
RCS temperature below 250 P and shiftly whilg the RCS temperature is below 250 P and the reactor head is installed.
3.
In order to start a reactor coolant 3.
Not applicable.
pump when the RCS temperature is g
below 250 P and no other reactor coolant pumps are running, the steam generator temperature of the loop in which th'e pump is to ge started shall be less than 50 P above the RCS temperature.
83 Amendment *!o. 54, Unit 1 Amendment No. 51, Unit 2
Bases:
Low Tenperature Overpressure Protection The repair period of 7 days is based on allowing sufficient time to offect renairs 3.3.2.G There are 3 means of protecting the using safe and proper procedures and upon RCS from overpressurization by a the operability of tne redundant PORV.
4.3.2.G pressure transient at low temperatures The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period to reach the (below 2500F).
The first type of restrictive conditions in the pressurizer protection is ensured by the operation orovides sufficient time to meet these and surveillance of the power operated conditions.
relief valves with a lift setting of 435 psig.
A singic power operated re-The OMS must be treated on a periodic basis consistent with lief valve (PORV) will relieve a pres-the need for its use. A channel functional test shall be sure transient caused by
- 1) a mass performed prior to enabling the overpressure protection addition into a solid RCS from a charg-system during cooldown and startup. This test shall be ing pump or
- 2) a heat input based on repeated monthly when the PORVs ::re required to be operable, a rcactor coolant pump being started in The channel functional test shall include verification of the an idle RCS and circulating water into backup air supply.
a steam generator whose temperature is 500F greater than the RCS temperature. (1)
Operability of each low temperature over pressure protection channel requires the control switch to be in the proper The second means of protection is position, the pressure point set, the PORV isolation valves e
r b
P
.V n
e 11 open, instrument and solenoid power on, and the PORV backup
. air supply changed.
as mentioned above.
The third neans of protection limits the pressurizer level to 25% and the The ' imitations and surveillance requirements on the ECCS equipment provides assurance that a mass.ddition pressurizer pressure to 100 nsig.
.a pressure transient caused by the inad-pressure transient can be relieved by the operation of vertent mass addition from a charging a single PORV or the limiting conditions placed on pump running for 10 minutes will be the pressurizer.
relieved by the large gas volume and low pressure present in the cressurizer The restrictions for startup of a RCP limits the heat as mentioned above.
Maintaining the input accident to within the relieving capabilities of pressurizer level below 25% will also a single PORV.
make the hi pressurizer level deviation 1
alarm available to the operator during (1) Pressure Mitigating Systems Transient Analysis a mass addition accident.
Results July 1977 Westinghouse Owners Group on RCS Overpressurization.
Amendment No. 54, Unit 1 Amendment No. 51, Unit 2 94 i
LL'11 TING' CONDITION FOR OPERATION SURVEILLANCE REQUIRE 1:NT 3.8 EMERGENCY CORE COOLING & CORE COOLING 4.8 EMERGENCY CORE,"OOLING & CORE COOLING SUPPORT S UPPORT Applicability:
Applicability:
Applies to the centrifugal charging, safety Applies to the centrifugal charging, safety injection, residual heat removal, component injection, residual heat removal, component cooling, service water and hydrogen control cooling, service water and hydrogen control systems per unit.
systems per unit.
- Objective:
Objective:
To establish 1.imiting conditions for the To establish the surveillance requirements applicable systems so as to assure for the above systems.
adequate emergency core cooling capability.
Specification:
Specification:
1.
Centrifugal charging pump system 1.
Centrifugal charging pump system (Table 4.8-1) systems shall be operable whenever A.
Surveillance and testing of the A.
The two centriEugal charging pump centrifugal charging pump systems the reactor is going from hot shutdown shall be performed as follows:
. to hot standby
( See 3. 3.2.G for low RCS temperature operation.}
1.
The centrifugal charging pumps shall be started manually from the control room each month.
Performance will be acceptable if the pump starts upon actuation, operates for at least 10 minutes on recirculation flow, 1
.I Amen:fment No. 54, Unit 1 Amendment No. 51, Unit 2 164
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREXENT 3.8 2.
Safety Injection pump system 4.8 2.
Safety injection pump System (Table 4.8-2)
A.
The two safety injection systems shall be operable whenever the A.
Surveillance and pump testing reactor is going from hot shutdown of the' safety injection system to hot standby.. (See 3. 3. 2.G for low shall be performed as follows:
RCS temperature operation. )
1.
The safety injection pumps shall be started manually from the control room each month.
Performance will be acceptable if the pump starts upon actuation, operates for at least 10 minutes on recirculation flow, and the dis-charge pressure and recirculation flow are within +10% of a point on the pump head curve.
i 2.
Valves MOV-SI8813 & MOV-SI8814 closing control switch contacts shall be tested for shorts quarterly.
Amendment tio. 54, linit i 168 1
i l
l l
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREF2NT
~
l l
3.8.5 Accumulator System
- 4. 8. 5 Accumulator System l
(Table 4. 8-4) i A.
The four accumulator systems shall I
satisfy the following conditions whenever A.
Surveillance and testing of the accumulator system shall be performed I
the reactor coolant system pressure as follows:
exceeds 1000 psig except as specified in 3.8.5.A.S.
(See 3. 3.2.G for low RCS l
temperature operation.)
1.
The pressure and+1evel of the secumulator tanks shall be 1.
Each accumulator shall be.
checked once a shift.
At each 54 pressyrized to at least 600 psig increase in-level, the boron and shall contain minimum of 770 ft3 concentration will be checked.
and a maximum of 818 ft3 of water.
2.
The accumulator boron con-centration shall be checked monthly.
2.
Each accumulator shall contain water borated to at least 2000 ppm.
3.
The accumulator check valve opera-3.
Each accumulator's isolation bility (SI-8948A, B,
C, and D and valve shall be open.
. (SI-8956A, B/ C, and D) will be verified at each refueling outage by opening the accumulator outlet isolation valve (MOV-SI8808A, B, C, and D) and verifying a decrease in accumulator level and a leak-age test to determine that no gross Valve leakage is experienced.
4.
Isolation Valves Not applicable.
Amendment No. 54, Unit 1 Amendment No. 51, Unit 2 174
B.
Records and/or logs re?.ative to the following 10.
Records of transient or operational items shall be recorde.1 in a manner convenient cycling for those components that for review and shall te retained for the life have been designed to operate safely of the plant.
for a limited number of transient or operational cycles.
1.
Substitution or replacement of principal items of equipment pertaining to nuclear
- 11. P.ecords of individual staff members s afety.
indicating qualifications, experience, training and retraining.
2.
Changes made to the plant as it is described in the Safety Analysis Report.
12.
Inservice inspections of the reactor coolant system.
3 Records of new and spent fuel inventory and assembly histories.
- 13. Minutes of meetings and results of reviews performed by the off-site and
- 4. (Deleted) on-site review functions.
5 Updated, corrected, and as-built 14 Records of secondary water sampling and drawings of the plant, gater quality.
6.
Records of plant radiation and contamination surveys.
7.
Records of off-site environmental monitoring surveys.
8.
Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20.
9.
Records of radioactivity in liquid and gaseous wastes released to the environment.
315 Amendment No. 54, Unit 1 Amendment No. 51, Unit 2
l I
6.6.3.c Special Reports 1
Reports on the following areas shall be as indicated:
l' AREA SUBMITTAL DATE a.
Primary Coolant Leakage Initial report within one year of initial criti-cality; 5 years after commercial service.
b.
In-Service Inspection Development First in-service inspection period after initial full power operation.
c.
In-Service Inspection Evaluation The requirements of Section 11 ASME Boiler Code (IS-620).
d.
Loose parts monitoring program On same date as in-service inspection report.
e.
Containment Building Structural Within 90 days following completion of each test.
Testing Report Q
f.
Lake Michigan Continuing Lake Study Within 60 days following the end of each 6 month Projects No. 1, 6, 9, 10, 11, 12 ***
routine operating report period. Each report shall contain tabular and graphical information, analysis and interpretation, of information obtained pursuant to each project.
g.
Waukegan Memorial Airport Expansion The expansion plans and status of such plans for the Plans Waukegan Memorial Airport will be reported yearly L
in the Annual Report including FAA #5010 report
[
h.
Overpressure Protection System Operation eithin 30 days of operation.
- Zion Nuclear Power Station Environmental Report, Section 2.3.6 Table S.
SEPCIAL REPORTS Table 6.6.2 Amendment No. 54, Unit 1
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328a