ML20134P320

Amends 90 & 80 to Licenses DPR-39 & DPR-48,respectively, Changing Tech Specs to Permit Full Pressure Testing of Containment & to Add Containment Air Lock Testing

ML20134P320
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	08/27/1985
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134P299	List: ML20134P297 ML20134P320 ML20134P337
References
NUDOCS 8509060241
Download: ML20134P320 (18)

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UNITED STATES aW J' go NUCLEAR REGULATORY COMMISSION

. WASHINGTON, D C. 20555 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.90 License No. DPR-39

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Commonwealth Edison Company (thelicensee)datedJanuary 30, 1985 and supplemented July 8, 1985, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Comission'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 Comission; 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

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l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment NoS0 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ha, ie Operating Reactors Br nch #1 Division of Licens

Attachment:

. Changes to the Technical Specifications Date of Issuance: August 27, 1985

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o s.ee gf o g UNITED STATES y m g NUCLEAR REGULATORY COMMISSION Q p WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.80 License No. DPR-48

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Comonwealth Edison Company (the licensee) dated January 30, 1985 and supplemented July 8, 1985, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Comission's rules and regulations set forth in 10 CFR Chapter I;

, . B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health s and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License l

No. OPR-48 is hereby amended to read as follows:

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~2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.80 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION I

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Operating Reactor ranch #1 Division of Licen

Attachment:

. Changes to the Technical Specifications Date of Issuance: August 27, 1985 O

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, ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 90 FACILITY OPERATING LICENSE N0. DPR-39 AMENDMENT NO. 80 FACILITY OPERATING LICENSE N0. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Pages 111 iii 212 212 213 213 21'4 214 214a

. 214b 215 215 216 216 217 217 218 . 218 l 219 219 220 220 221 221 G

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Table of Contents (Continued)

SURVEILLMCE LIMITING CONDITION FOR OPERATION REQUIREMENT pag 3.7 Steam Generator Emergency Heat Removal

3. 7.1 4.7 156 Steam Generator Safety Valves 4.7.1 3.7.2 156 Auxiliary Feedwater Pump System 4.7.2 3.7.3 Auxiliary Feedwater Supply System 158 4,7.3 159a Bases 3.8 Emergency Core Cooling and Core Cooling Support 3.8.1 4.8 164 Centrifugal Charging Pump System 4.8.1 3.8.2 164 Safety Injection Pung System 4.8.2

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3.8.3 Residual Heat Removal Pump System 168 3.8.4 4.8.3 170 System Testing of Centrifugal Charging, Safety 4.8.4 173 -

Injection, and Residual Heat Removal Pump Systems 3.8.5 Accumulator System 3.8.6 4.8.5 174 Component Cooling System 4.8.6 3.8.7 Service Water Systw 175 3.8.8 Hydrogen Control Systems 4.8.7 178 3.8.9 4.8.8 180 Equipment for Evaluating Post LOCA 4.8.9 Bases 184 3.9 Containment Isolation Systems 3.9.1 Isolation Valve Seal Water System 4.9 ' 197 3.9.2 4.9.1 197 Penetration Pressurization Systems 4.9.2 3.9.3 198 Containment Isolation Valves 4.9.3 3.9.4 Main Steam Isolation Valves and 8ypasses 199 3.9.5 4.9.4 200 Containment Integrity 4.9.5 Bases 201 3.10 Containment Structural Integrity 3.10.1 4.10 212 Containment Leakage Rate Testing 4.10.1 3.10.2 212 Containment Air Locks 4.10.2 3.10.3 Containment Tendons 214a

3. 10.4 4.10.3 215 End Anchorages and Concrete 4.10.4 3.10.5 Containment Pressure 217 3.10.6 Containment Temperature 4.10.5 219 8ases 4.10.6 219 3.11 Radioactive Liquids Bases 4.11 222 3.12 Radioactive Gases Bases 4.12 230 i

0521t 111 Amendment Nos. 90 and 80 0230A

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.10 CONTAINNENT STRUCTURAL INTEGRITY (per unit) 4.10 CONTAINNENT STRUCTURAL INTEGRITY (per unit) i GBJECTIVE: OBJECTIVE:  !

.To insure that the containment structure To establish the testing requirements to meets its design requirements throughout assure containment structural integrity.

plant life.

1. Containment Leakage Rate Testing SPEC.lFICATION:

A. Surveillance and testing of the

1. Containment Leakage Rate Testing -

A. Containment Leakage Rate shall containment shall be performed as follows:

be limited to: ,

1. The containment Type A

1. An overall integrated leakage rate shall be leakage rate of:

determined in conformance

a. with 10CFR 50 Appendix J.

Less than or equal to La , 0.10 percent by a. The leakage rate test weight of the containment air per 24 shall be performed at or above the design basis hours at Pa (4T accident pressure Pa psig), or (47 psig),. or at or above the reduced pressure P t

b. Less than or equal to (25 psig).

Lt , where 1.t is as computed in 10CFR 50 Appendix J, is the maximum allowable leakage rate at pressure Pg (25 psig)

2. A combined leakage rate of less than or equal to 0.60 La, for all penetrations and valves sub. lect to Type B and C tests, when pressurized to P a-APPLICABILITY: Modes 1, 2, 3, 4 and 7 Amendment Nos. 90 and 80 nn1At/nR1Qt '1'

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.1.A (Continued) 4.10.1.A. 1. c. The maximum allowable leakage rate L a or L t. as ACTION: applicable, shall be computed in accordance with the With either (a) the measured overall appropriate paragraphs of integrated containment leakage rate 10CFR 50 Appendix J.

exceeding 0.75 La or 0.75 Lg, as applicable, or (b) with the measured 2 , Type B and C tests (except air combined leakage rate for all penetrations lock tests) shall be performed at and valves subject to Type B and C tests Pa or above in accordance with exceeding 0.60 La, restore the overall the provisions of the appropriate integrated leakage rate to les; than or Section of 10CFR 50 Appendix J.

equal to 0.75 L or less than or equal to 0.75 Lg, as app,licable, and the combined 3. Air locks shall be tested and leakage rate for all penetrations subject to demonstrated OPERABLE per '

Type B and C tests to less than or equal to Surveillance Requirement 4.10.2.

0.60 La prior to entering MODE 4.

4. The Type A, 8, and C leakage rate tests shall be considered to be satisfactory if the acceptance criteria delineated in 10CFR 50 Appendix J are met.

5. Leakage from containment isolation valves sealed by the Isolation Valve Seal Water system may be excluded from the combined Type B and C leakage rate.

I Amendment Nos. 90 and 80 0838t/0839t 213

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.1.A (Continued) 4.10.1.A. 6. The retest schedules for Type A. l 8, and C tests shall be in accordance with the appropriate Section of 10CFR 50 Appendix J.

7. Inspection and reporting of tests shall be in accordance with the

. appropriate Section of 10CFR 50 Appendix J.

Amendment Nos. 90 and 80 0838t/0839t 214 -

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LIMITING CONDITIONS FOR OPERATION SVRVEILLANCE REQUIREMENT 3.10.2 Containment Air Locks 4.10.2 Containment Air Locks A. Each containment air lock shall be A. Each air lock shall be demonstrated OPERABLE with: OPERABLE:

1. Both doors closed except when 1. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each the air lock is being used for opening (except when the air normal entry and exit through lock is being used for multiple the containment, then at least entries, then at least once per one air lock door shall be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />);

closed, and a. Verify that the leakage

2. The air lock leakage rate, when rate from the air lock door combined with other Type B and seals is less than or equal C test results, shall be less to 1.0 SCFH at a test than or equal to 0.60 La at pressure (Pt r) of greater 47 psig (Pa). than or equal to 2.5 psig; or verify that the leakage rate from the air lock door APPLICABILITY: Modes 1, 2, 3, 4 and 7 seals is less than or equal to 4.75 SCFH at a test pressure (P t ) of greater ACTION: than or equal to 10.0 psig.

a.) With one containment air lock door inoperable: b. If the air lock door seal

1. Maintain at least the OPERABLE test identifies a leakage air lock door closed and either rate greater than 1.0 SCFH restore the inoperable air lock at a test pressure (Pt r) door to OPERABLE status within of greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE 2.5 psig or 4.75 SCFH at a air lock door closed. test pressure (P t) Of

2. Operation may continue until greater than or equal to performance of the next 10.0 psig, then an overall required overall air lock air lock leakage test shall leakage test provided that the be performed at a pressure

. OPERABLE air lock door is (Pa) of 47 psig or '

verified locked closed at least greater. The acceptance once per 31 days, criteria shall be as stated

3. Otberwise be in at 1 cast MODE 3 in 3.10.2. A.2.

within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

07830/07840 214a Amendment Nos. 90 and 80

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.2 (Continued) 4.10.2.A (Continued)

4. The provisions of Technical 2. By conducting overall air lock Specification 3.0.4 are not leakage tests at a pressure (Pa) Of applicable. 47 psig or greater and verifying the overall air lock leakage is within b.) With the containment air lock the limit:

inoperable, except as a result of an a. At 6 month intervals inoperable air lock door, neintain at b. Prior to entering Mode 4; if in least one air lock door closed; restore Mode.5 greater than or equal to 7 the inoperable air lock to OPERABLE days and containment integrity status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at has been broken (both doors open).

least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within the following 30 3. At least once per 6 manths by hours. verifying that only one door in each air lock can be opened at a time.

i 07830/07840 214b Amendment Nos. 90 and 80

. - - -_ _ = . _ _ _

LIMITING CDN0lTIDN FOR OPERATIDN SURVEILLANCE REQUIREMENT

! 3.10.3. Containment Tendons 4.10.3. Containment Tendons I

.1. Nine containment tendons shall be A.

examined periodically, Nine containment tendons shall be examined l periodically to detect excessive relaxation A full examination as specified under of the post tensioning force or to discover 4.10.3. A vill be perf ormed on one possible material deterioration. The containment only. A visual inspection inspection shall be carried out at five year only shall be performed on the other intervals.

containment.

A quantitative analytical report covering results of each inspection shall be submitted and shall especially address the following conditions, should they develop:

(1) Broken wires.

(2) Measured 11ft off forces lower than the final pre-stress force considered in the design.

(3) Unusual changes in corrosion conditions l

or sheathing filler properties.

The 9 tendons will be randomly selected from the following tendon types and inspected as l described.

To develop a history and for correlating the observed data, one tendon of each type may be kept unchanged efter the initial selection.

Tendons that showed deficiencies in previous surveillances may be substituted for the randomly chosen tendons.

9 Amendment Nos. 90 and 80 0838t/0839t 215

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LIMITING COMOITION FOR OPERATION SURVEILLANCE REQUIREMEhi 3.10.3. (Continued) 4.10.3 (Continued) l l Measure l Measure Tendon l Tendon Force l Force & Remove l only l 1 Wire Per Tendon i

Tendon Type l Total I (**) I (#1 Dome

• l 3 l 2 l 1 Horizontal .l- 3 l 2 l 1 Vertical l 3 l 2 l 1 l 9 l l

(**) 1. Measure lift off force.

2. Increase load to max. allowable overstressing stress and record elongation.

3. Reduce load and. seat anchorhead back on shtms.

4. Make lift off reading.

5. Check for broken wires.

NOTE: The above may be carried out for each l tendon end independently.

(#) 1. Measure lift off force.

2. Remove shims and reduce load to zero.

3. Remove one wire per tendon.

4. Check for broken wires.

5. Retension the tendon by increasing the load to maximum allowable overstressing stress and record elongation at 5 approx. equal steps.

6. Reduce load and seat anchorhead back on shims at the same lift.off stress as measured above in 1.

7. Make lift off reading.

8. Check for broken wires.

NOTE:

The above has to be carried out from both ends of the dome and horizontal tendons

.. simultaneously. Vertical tendons are always tested from the top end only.

• One tendon must be chosen from each of the three

-0838t/0839t groups of dome tendons.

216 Amendment Nos. 90 and 80

LIM 111NG CON 01110N FOR OPERA 110N SURVEILLANCE REQUIREMENT 3.10.3.A. (Continued) 4.10.3.A.

. (Continued)

Tensile tests shall be performed on specimens from the center and each end of each wire removed. The wires removed shall be examined for significant corrosion or pitting. Should such activity be discovered tensile specimens shall be located to

, include affected areas.

Where the inspection reveals pitting or corrosion sufficient to affect the load carrying ability of the tendon, other wires from other surveillance-tendons removed and inspected.in the same location shall be The sheathing filler shall be sampled and inspected for changes in physical appearance and chemical composition.

B. Nine containment tendons shall be examined B.

periodically. Since both units have A visual examination of the tendons selected as identical containment structures, neither described under 4.10.3.A. Will be performed to the unit displays environmental or other extent practical, without dismantling load bearing l apparent differences, both units are located components of the anchorage. The examination shall at the same plant site, and both units were include inspection for broken wires; inspection of built under continuous construction, the buttonheads for cracks, corrosion, or other containment structure of the other unit will deterioration; and inspection of bearing plates and be subjected to a partial examination as shtms for deformation and cracks. Grease in tendon spelled out under 4.10.3.B. end caps shall be examined. The anchorhead components shall be verified operable.

3.10.4. End Anchorage and Concrcte 4.10.4 End Anchorage and Concrete Surveillance l

A. The end anchorages and adjacent concrete surface The End Anchorage and adjacent concrete surfaces shall be inspected periodically, shall be inspected periodically. The inspection shall be carried out at 5 year intervals.

The inspections made shall include:

(1) Visual inspection of the end anchorage concrete 0838t/0839t exterior surfaces.

217 Amendment Nos. 90 and 80

W-LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l 3.10.4. (Continued) 4.10.4. (Continued)

(2) A determination of the temperatures of the 11ner plate area or containment ir.terior surface in locations near the end anchorage concrete under surve111ance based on ava11able

' temperature gauges and accessibility.

(3) Measurement of concrete temperatures at specific end anchorage concrete surfaces being inspected.

(4) The mapping of the predominant visible concrete crack patterns.

(5) The measurement of the crack widths, by use of optical means or by thickness gages.

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0838t/0839t 218

. '. I LIMITING CONDITION FOR OPERATION SURVElli.ANCE REQUIREMENT 3.10.5. Containeent Pressure 4.10.5. Containment. Pressure If the containment internal pressure exceeds The containment pressure shall be verified 1.0 psig or the internal vacuum exceeds 1.$ once a shif t.

psig, the condition shall be corrected inenediately or the reactor shall be brought to the hot shutdown condition within 4 ho:rs.

6. Containment Temperature 6. Containment Tenperature If the containment ambient temperature The containment temperature shall be exceeds 120*F or is less than 65'F the verified once a shift.

condition shall be corrected insnediately or the reactor shall be brought to the hot shutdown condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

7. The provisions of Specific'ation 3.0.3 are 7. Not Appilcable not applicable to Specification 3.10.3, 3.10.4, 3.10.5 and 3.10.6.

219 Amendment Nos. 90 and 80

Basis: .

3.10 While a reactor is operating the internal environment of the containment will reach a maximum ambient temperature of 120*r and a maximum pressure of 1.0 psig. With these '.

Initial conditions the peak accident pressure reached will still be below a containment design pressure of 47 psig. (1) l The minimum operating pressure of -1.5 psig is based on the expected lower limit of containment pressure following cooldown from 120*F to the minimum design temperature of 65'F. (2)

[1)FSAR,AnswertoQuestion14.28 (2) FSAR, Answer to Question 9.9 4

I Amendment Nos. 90 and 80

Basis:

4.10 Prior to' initial-operation, a containment will The tendon surveillance is in general agreement be strength tested at 54 psig and then will be with Regulatory Guide 1.35 Rev. 2. (3) This l l 1eak-tested. The acceptance criterion for this surveillance program may be carried out during pre-operational leakage rate test has been reactor operation since the containment design established as 0.1% of the containment volume provides that one tendon each in the Dome, Wall per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 47 psig. (1) With this leakage Horizontal and Wall Vertical can be detensioned rate and with minimum engineered safeguards without impatring the safety of the structure.

systems operating, the public exposure would be well below the 10CFR100 values in the event of a The end anchorage surveillance is intended to design basis accident. (2) detect deterioration of the anchorage structure which would be easily visible.

The performance of a periodic integrated leak rate test (Type A),and local penetration tests (Type B and C) during containment life provides a current assessment of potential leakage from a (3) FSAR, Answer to Question 5.-56.

containment during accident conditions. These periodic tests will be performed at pressures

sufficiently high to provide an accurate measurement of the leakage rate; this pressure will be at least 50 percent of design accident pressure for the Type A tests and at least design accident pressure for the Type B and C tests.

(1) FSAR Section 5.2 (2) FSAR Section 14.3.5 l

Amendment Nos. 90 and 80

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