ML19261C338
| ML19261C338 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/20/1979 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19261C336 | List: |
| References | |
| TAC-08321, TAC-11245, TAC-59183, TAC-8321, NUDOCS 7903220280 | |
| Download: ML19261C338 (50) | |
Text
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PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT CCMPANY TROJAN NUCLEAR PLANT Operating License NPF-1 Docket 50-344 License Change Application 26, Revisio' 1 This License Change Application is submitted in support of Licensee's required action to update the Inservice Inspection and Inservice Testing Programs for ASME Section XI Boiler and Pressure Vessel Code Class 1, 2, and 3 components and systems in accordance with 10 CFR 50.55.
PORTLAND GENERAL ELECTRIC (X)MPANY By C. Goodwin, Jr'.
Assistant Vice President Thermal Plant Operation and Maintenance Subscribed and sworn to before me this 20th day of March 1979.
A4
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Notary Public of Orggon My Commission Expires:
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790322028o 4kklA2
LCi 26, Revision 1 Page 1 of 12
_ LICENSE CHANGE APPLICATION 26 Proposed replacement pages to Appendix A of Facility Operating License NPF-1 are provided as Attachment 1.
1.
Page 3/4 0-2 (and 3/4 0-3):
Add a new Specification 4.0.5 as follows:
"4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows :
a.
Inservice inspection of ASNI Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure vessel Code and applicable Addenda as required by 10 CFR 50 3ection 50.55a(g),
3 except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Sec-tion XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies for Addenda Terminology for Performing Inservice Inservice Testing Activities Testing Activities Weekly At leas t once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At le as t once per 276 days Yearly or annually At least once per 366 days c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspec-tion and testing activities shall be in addition to other specified Surveillance Requirements.
LCA 26, Revision 1 Page 2 of 12 LICENSE CHANGE APPLICATION 26 Nothing in the ASME Boiler and Pressure e.
Vessel Code shall be construed to super-sede the requireme:its 3f any Technical Specification."
2.
Pages 3/4 1-7 and 3/4 1-8:
Delete Item 1 of Specification 4.1.2.1.a, and combine Item 2 with opening phrase, to read as follows :
"a.
At leas t once per 7 days by verifying that the temperature of the flow path is 2,65*F when a flow path from the boric acid tanks is used, and".
3.
Page 3/4 1-11:
Change Specification 4.1.2.3 to:
"4.1.2.3 The above required charging pump shall ba demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of 2.2400 psig when tested pursuant to Specification 4.0.5."
4.
Page 3/4 1-12:
Change Specification 4.1.2.4 to:
"4.1.2.4 At least two charging pumps shall be demon-strated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of 2,2400 psig when tested pursuant to Specification 4.0.5."
5.
Page 3/4 1-13 :
Change Specification 4.1.2.5 to:
"4.1.2.5 The above required boric acid transfer pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of 2105 psig when tested pursuant to Specification 4.0.5."
6.
Page 3/4 1-14:
Change Specification 4.1.2.6 to:
"4.1.2.6 The above required boric acid transfer pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of 2,105 psig when tested pursuant to Specification 4.0.5."
7.
Page 3/4 4-4:
a.
Change the tolerance for the safety valves in Specifi-cation 3.4.3 from +1% to +2%, -3%.
b.
Change Specification 4.4.3 to:
"4.4.3 No additional Surveillance Requirements other than those required by Specification 4.0.5."
LCA 26, Revision 1 Page 3 of 12 LICENSE CHANGE APPLICATION 26 8.
Page 3/4 4-6:
In Specification 4.4.5.2, delete the third sentence a.
in the initial paragraph beginning with " Steam generator tu b e s.... "
b.
Specification 4.4.5.2.b, reword as follows :
"b. The first sample of tubes selected for each inservice inspection (subsequent to the pre-service inspection) of each steam generator shall include:"
9.
Page 3/4 4-7:
a.
Add a new Subsection 3 to Specification 4.4.5.2.b as follows :
"3.
A tube inspection (pursuant to Specifica-tion 4.4.5.4.a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection."
b.
Reword Specification 4.4.5.2.c as follows :
"c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections include those portions of the tubes where imperfections were previously found."
10.
Page 3/4 4-8:
Reword Specification 4.4.5.3.b as follows :
"b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Cate-gory C-3, the inspection frequency shall be increased to at least once per 20 months.
The increast in inspection frequency shall apply until the subsequent inspections satis fy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months."
LCA 26, Revision 1 Page 4 of 12 LICENSE CHANGE APPLICATION 26 11.
Page 3/4 4-9 and 3/4 4-9a:
Specification 4.4.5.4:
a.
Subsection 5, delete the third (the last) sentence.
b.
Add a new Subsection 9 as follows :
"9.
Preservice Inspection means an inspection of the 6211 length of each tube in each steam gen-erator performed by eddy current techniques prior to service establish a baseline condition of the ' tubing. This inspection shall be per-formed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections."
c.
In Specification 4.4.5.5.b, delete the words "... included in the Annual Operating Report..." and add the new phrase
"... reported on an annual basis... ".
12.
Page 3/4 4-29:
Replace Specifications 3.4.10 and 4.4.10 with the following:
"3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY:
ALL MODES ACTION:
With the structural integrity of any ASME Code a.
Class I component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System tempera-ture more than 50 *F above the minimum tempera-ture required by NDT considerations, or comply with ACTION item d below.
b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity
LCA 26, Revision 1 Page 5 of 12 LICENSE CHANGE APPLICATION 26 of the affected component (s) to within its limit or isolate the af fected component (s) prior to increasing the Reactor Coolant System temperature above 200*F, or comply with ACTION item d below.
With the structural integrity of any ASME Code c.
Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected couponent(s) from service, or comply with ACTION item d below.
d.
If the requirements of the above ACTION items are not met, in lieu of the requirements of Specification 3.0.3,,an evaluation can be performed to determine the consequences of continuing to operate with reduced structural integrity or with a temporary repair msde to the affected component (s), or be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The provisions of Specification 3.0.4 are not e.
applicable.
SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements 'of Specifica-tion 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Posi-tion C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
4.4.10.2 The operability of the hydraulic pipe snubbers shall be demonstrated initially at least once after not less than 4 months or more than 6 months of operation and then at least once per 18 months by verifying that the snubber hydraulic fluid reservoirs are filled to between their minimum and maximum level indication marks."
13.
Delete Pages 3/4 4-30 through 3/4 4-49.
14.
Pages 3/4 5-4 through 3/4 5-6a:
Make the following changes to Specification 4.5.2:
a.
Specification 4.5.2.b:
(1) Delete Specifications 1, 2, 3 and 4.
(2) Combine old Specification 5 on Page 3/4 5-5 with the introductory phrase of this Specification on Page 3/4 5-4.
LCA 26, Revision 1 Page 6 of 12 LICENSE CHANGE APPLICATION 26 b.
Delete Specification 4.5.2.c.
c.
Add a new Specification 4.5.2.h as follows :
"h.
By verifyi.ng that each of the _ollowing pumps develops the indicated discharge pressure on recirculation flow when test.ed pursuant to Specification 4.0.5:
1.
Centrifugal charging pump >2400 psig 2.
Safety injection pump 21455 psig 3.
Residual heat removal pump 2,165 psig" 15.
Page 3/4 6-10:
a.
Change Specification 4.6.2.1.a to:
"a.
By verifying, that on recirculation test line flow, each pump develops a discharge pressure of 2,228 psig at a flow of 2,586 gpm for FE-2066 and >227 psig at a flow of 2,592 gpm for FE-2067 when tested pursuant to Specification 4.0.5."
b.
Delete old Specifications 4.6.2.1.a.1 through 4.
Redesignate old Specification 4.6.2.1.a.5 on Page 3/4 6-11 c.
as 4.6.2.1.b and add at the beginning:
"At least once per 31 days by...".
16.
Page 3/4 6-11:
a.
Redesignate old Specification 4.6.2.1.b as 4.6.2.1.c.
b.
Delete old Specification 4.6.2.1.b.1 (new Specifica-tion 4.6.2.1.c.1) and renumber remaining specifications accordingly.
c.
Redesignate old Specification 4.6.2.1.c as 4.6.2.1.d.
17.
Page 3/4 6-12:
In Specification 4.6.2.2.a, delete Item 1 and include Item 2 in one sentence beginning with heading of a.
18.
Page 3/4 6-13:
In Specification 4.6.2.2.c, delete Item 1 and combine Item 2 with heading of c.
19.
Page 3/4 6-15:
In Specification 4.6.3.1.1:
a.
Delete Item a.
b.
Combine Item b with the beginning sentence of 4.6.3.1.1, delete the words "immediately" and "above" and replace the word "the" in the last line, to read as follows:
LCA 26, Revision 1 Page 7 of 12 LICENSE CHANGE APPLICATION 26 "4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time."
20.
Page 3/4 6-16:
'.n Specification 4.6.3.1.2, delete Items e and d.
a.
b.
Delete old Specification 4.6.3.1.3 and replace with the following:
"4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Speci-fication 4.0.5."
21.
Page 3/4 7-1:
Change Specification 4.7.1.1 to the following:
"4.7.1.1 No additional Surveillance Requirements other than those required by
- acification 4.0.5 "
22.
Page 3/4 7-4, Table 4.7-1:
Change the tolerances for the lif t settings from +1% to +2%, -3%.
23.
Page 3/4 7-6:
a.
Specification 4.7.1.2.1.a:
Delete Items 3 and 4 and redesignate Item 5 as b; add at the beginning of new b:
"At least once per 31 days by...".
b.
Specification 4.7.1.2.1.b:
(1) Redesignate thic specification as c.
(2) Delete Item 1 and renumber Items 2 and 3, accordingly.
24 Page 3/4 7-13:
Change Specification 4.7.3.1.a and b to the following:
"a.
At least once per 31 days, by verifying that each valve (manual, power operated or au;omatic) ser-vicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 montns during shutdown, by verifying that each automatic valve serving safety-related equipment actuates to its correct position on a safety injection test signal."
m,,.
mis a,s b
LCA 26, Revision 1 Page 8 of 12 LICENSE CHANGE APPLICATION 26 25.
Page 3/4 7-14:
Delete specifications, leave page blank and add the phrase:
"This page lef t intentionally blank".
26.
Page 3/4 7-15.
Change Specification 4.7.4.1.a and b to the following:
"a.
At least once per 31 dars, by verifying that each valve (manual, power operated and. automatic) servic-ing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position, b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equipment actuates to its correct position on a safety injection test signal."
27.
Page 3/4 7-16: Delete specifications, leave page blank and add the phcase:
"This page left intentionally blank".
28.
Add a new Page B 3/4 0-3 (Specification BASES 4.0.5) as follows:
"4.0.5 This specification ensures that inservice inspec-tion of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
Relief from any of the above requirements has been pro-vided in writing by the Commission and is not a part of these Technical Specifications.
This specification includes a clarification of the fre-quencies for performing the inservice inspection and testing activities requi.ed by Section XI of the ASME Boiler and Presaure V?ssel Code and appli able Addenda.
c This clarificattod is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification, the more restric-tive requirements of the Technical Specifications take precedence over the ASME Boiler and Fressure Vessel Code and applicable Addeada.
For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry lato an OPERATIONAL MODE or other specified applicabilit etw '. tion takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to
LCA 26, Revision 1 Page 9 of 12 LICENSE CHANGE APPLICATION 26 normal operation. And for example, the Technical Speci-fication definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of per-forming its specified function for up to 24 hr before being declared inoperable."
29.
Page B 3/4 4-1:
In Specification 3/4.4.2 and 3/4.4.3, delete the comma and words "..., 1974 Edition," in the last line of the last paragraph.
30.
Page B 3/4 4-2a:
Specification 3/4.4.5:
In the fif th line of the first paragraph (near the begin-a.
ning of the second full sentence), add an "s" to " plant".
b.
In the last line of the second paragraph, correct the spelling of " original".
31.
Page B 3/4 4-9:
Specification 3/4.4.10:
a.
Replace the first paragraph with the following two paragraphs:
"3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an accept-able level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Components of the Reactor Coolant System were designed to provide access to pe rmit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1971 Edition and Addenda through Winter 1972."
b.
In the last line of the original second paragraph (now third paragraph), replace ".. 5 year... " with ".. 40 month... ".
LCA 26, Revision 1 Page 10 of 12 LICENSE CHANGE APPLICATION d 32.
Page B 3/4 4-10:
Specification 3/4.4.10:
a.
Add the following sentence at the end of the firsc paragraph:
"The 29-in. Reactor Coolant System piping requires special ultrasonic technique because it is centrifu-gally cast austenitic steel."
b.
Delete the third paragraph in its entirety.
c.
In the fif th (new fourth) paragraph:
(1) Replace "The Quality Group..." with "ASME...".
(2) Delete the second and third sentencas of this paragraph (all but the first sentence).
(3) Add the following sentence to this paragraph:
" Pressure test criteria for Class 2 components are defined in ASME XI, Article IWC-5000; pressure test criteria for Class 3 components are defined in ASME XI, Article IWD-5000."
REASON FOR CHANGE License Change Application 26 was originally issued and submitted to the NRC on April 22, 1977 to update the ASME Code reference for Inservice Inspection (ISI) in the Trojan Technical Specifications (Appendix A to Facility Operating License NPF-1).
No attempt was made to incorporate the ASME Code requirements for Inservice Testing (IST) of pumps and valves in LCA 26.
The Code of Federal Regulations, 10 CFR 50.55a(g),
requires all nuclear plant licensees (holders of Construction Permits as well as Operating Licenses) to review and update their ISI and IST programs every 40 months and 20 months, respectively.
Since the Trojan Facility Operating License was issued prior to March 1,1976, the require-ment for IST of pumps and valves does not become effective until the start of the next regular 40-month period which is September 20, 1979.
Subsequently, PGE received guidance in regard to the submittal of IST programs from the NRC (A. Schwencer letter to C. Goodwin, Jr., of January 13, 1978) and a request for additional information in regard to LCA 26 from the NRC (A. Schwencer letter to C. Goodwin, Jr., of March 16, 1978). Additionally, the NRC has proposed a revision to 10 CFR 50.55a(g) providing more flexibility in the use and application of the varie s editions of and Addenda to the Code and increases the IST interval to that of ISI, and increases both to 120 months (4? years).
LCA 26, Revision 1 Page 11 of 12 LICENSE CHANGE APPLICATION 26 Therefore, this revision to LCA 26 has been prepared to incorporate the more recent requirements and requests for information in accordance and compliance with 10 CFR 50.55a(g).
Specifically, the reasons for change are as follows:
1.
A new Specification 4.0.5 is needed to refer to ASME Section XI for ISI and IST of pumps and valves.
This latter addition is a revision to previously submitted LCA 26.
2.
The various surveillance requirements in the Technical Specifications for Class 1, 2, and 3 pumps and valves need to be changed to reference ASME Section XI and 10 CFR 50.55a(g) via Specification 4.0.5.
The safety-related values for determining operability are to remain in the Technical Specifications. Valve closing times for Containment isolation valves remain in the Technical Specifications.
Pump discharge pressures and flows, where applicable, remain in the Technical Specifications.
3.
In general, valve cycling to determine operability is incorporated in the IST program for valves and is no 1 cager required to be in the Technical Specifications.
SAFETY EVALUATION The changes proposed by this LCR have been reviewed and determined to not ccnstitute an unreviewed safety question. No new accidents are created and the probability and consequences of accidents previously considered remain unchanged.
No effects upon the environment will result from these changes in surveillance testing of ASME Class 1, 2 and 3 equipment and components.
The changes proposed by this LCR are in accordance with NUREG-0452, dated June 15, 1978.
NUREG-0452 is the NRC publication of Standard Technical Specifications for Westinghouse PWRs. As such, NUREG-0452 has been reviewed and determined to not constitute an unreviewed safety question by the NRC.
The changes in the surveillance requirements of ASME Class 1, 2 and 3 equipment and components in the Trojan Technical Specifications are due to NUREG-0452, 10 CFR 50.55a(g), and Section XI of the ASME Boiler and Pressure Vessel (BPV) Code.
Safety-related acceptance criteria for certain pumps and valves are retained in the surveillance requirement Technical Specifications.
Certain pump discharge pressures and flows that are necessary to mitigate the consequences of an accident remain in the Technical Specifications, although the testing of those pumps will now be performed in accordance with Section XI of the ASME BPV Code.
Likewise, certain valve closing times such as for Containment isolation valves remain in the Technical Specifications, whereas most valve cycling for operability has been transferred to the IST program.
The removal of the specific require-ments to cycle certain safety-related valves to determine operability
LCA 26, Revision 1 Page 12 of 12 LICENSE CHANGE APPLICATION 26 from the Technical Specifications and insertion in the IST program does not indicate a decrease in or degradation of plant safety; the testing requirements of the IST program are just as stringent and tightly con-trolled. A draf t copy of the IST of pumps and valves program is attached for information (Attachment F).
The requirement to start a pump from the control room as a part of the operability test is deleted since no safety-related pumps depend upon a manual start from the control room to accomplish their design functions.
Furthermore, the control circuitry for pump starts can be verified by other means than actually starting a pump.
The surveillance requirements for steam generators are only slightly changed from the present Trojan Technical Specifications.
Furthe rmore,
such changes are in accordance with NUREG-0452, are mostly administra-tive, and would not result in a decrease in safety margin of the steam generators.
In general, the testing requirements of pumps and valves are changed in a manner that is likely to improve equipment performance and reliability by more stringent testing criteria and by testing on a more practical frequency.
It is felt that the plant safety margin would be increased vice decreased by this LCR.
BASIS FOR DETERMINATION OF AMENDMENT CLASS This determination is not applicable because this submittal is a revision to LCA 26, which had been submitted to the NRC prior to the effective date of 10 CFR 170. As such, no fee is required.
SCHEDULE CONSIDERATIONS The next 40 month (or 120 month) interval for ISI and IST commences on September 20, 1979. As such approval of this LCA is requested at least 30 days prior to that date in order to be in compliance with 10 CFR 50.55 upon September 20, 1979.
GAZ/4kklA3
LCA 26, Revision 1 Page 1 of 37 3/4.0 APPLICASILITY SURVEILLANCE REQUIREMENTS (Continued) b.
A total maximum combined interval time for any 3 consecutive surveillance internals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Perfonnance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance Require-ments do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
The provisions of Specification 4.0.4 are not applicable to the perform-ance of surveillance activities associated with fire protection technical specifications 4.3.3.7.1, 4.3.3.7.2, 4.7.8.1.1, 4.7.8.1.2, 4.7.8.1.3, l
4.7.8.3 and 4.7.9 until the completion of the initial surveillance interval associated with each specification.
4.0.5 Surveillance Requirements for inse~rvice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2 and 3 compo-nents and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be perfonned in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Sec-tion 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Yessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
TROJAN-UNIT 1 3/4 0-2
LCA 26, Revision 1 Page 2 of 37 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)
ASME Boiler and Pressure Vessel Code and applicable Required frequencies Addenda terminology for for performing inservice inservice testing activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days.
c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveil-lance Requirements.
e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
TROJAN-UNIT 1 3/4 0-3
LCA 26, Revision 1 Page 3 of 37 REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of tbt following boron injection flow paths shall be OPERABLE:
a.
A flow path from the boric acid tanks via either a boric acid transfer pump or a gravity feed connection and charging pump to the Reactor Coolant System if only the boric acid storage tank in Specification 3.1.2.7a is OPERABLE, or b.
The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if only the refueling water storage tank in Specification 3.1.2.7b is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demon-strated OPERABLE:
a.
At least once per 7 days by verifying that the tempera-l ture of the flow path is >65*F when a flow path from the boric acid tanks is used, and TROJ AN-UNIT 1 3/4 1-7
LCA 26, Revision 1 Page 4 of 37 REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continuet" b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
TROJAN-UNIT 1 3/4 1-8
LCA 26, Revision 1 Page 5 of 37 REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.3 The above required charging pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of >2400 psig when tested pursuant to Specification 4.0.5.
TROJ AN-UNIT 1 3/4 1-11
LCA 26, Revision 1 Page 6 of 37 REACT 1VITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With only one cnarging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY witnin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of >2400 psig when tested pursuant to Specification 4.0.5.
TROJAN-UNIT 1 3/4 1-12
LCA 26, Revision 1 Page 7 of 37 REACTIVITY CONTROL SYSTEMS BORIC ACID TRANSFER PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid transfer pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid transfer pump of Specification 3.1.2.la is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no boric acid transfer pump OPERABLE as required to complete the flow path of Specification 3.1.2.la, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one boric acid transfer pump is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required boric acid transfer pump shall be demon-strated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of >105 psig when tested pursuant to Specification 4.0.5.
TROJAN-UNIT 1 3/4 1-13
LCA 26, Revision 1 Page 8 of 37 REACTIVITY CONTROL SYSTEMS BORIC ACID TRANSFER PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 At least one boric acid transfer pump in the boric injection flow path required by Specification 3.1.2.2a shall be OPERABLE if the flow path through the boric acid transfer pump in Specification 3.1.2.2a is OPERABLE.
APPLICABILITY:
MODES 1, 2s 3 and 4.
ACTION:
With no boric acid transfer pump OPERABLE, restore at least one boric acia transfer pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or De in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 1% ak/k at 200*F; restore at least one boric acid transfer pump to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.6 The above required boric acid transfer pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of >105 psig when tested pursuant to Specification 4.0.5.
TROJ AN-UNIT 1 3/4 1-14
LCA 26, Revision 1 Page 9 of 37 REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3 All pressur'zer code safety valves shall be OPERABLE with a lif t setting of 2485 P'dG + 2%, -3%.
l APPLICABILITY:
40ES 1, 2 and 3.
ACTION:
With a pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
TROJAN-UNIT 1 3/4 4-4
LCA 26, Revision 1 Page 10 of 37 s
REACTOR C0OLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing T above 200*F.
avg SURVEILLANCE REQUIREMENTS 4.4.5.1. Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classifi-cation, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservie.
l insection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
TROJAN-UNIT 1 3/4 4-6
LCA 26, Revision 1 Pace 11 of 37 REACTOR C0OLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1.
All nonplugged tubes that prev'ously nad detectable wall penetrations (>20%).
~
2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube.
If any selected tube does not pennit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following thrce categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage. calcul ations.
TROJAN-UNIT 1 3/4 4-7
LCA 26, Revision 1 Page 12 of 37 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - The above required inservice inspections of steam generator tuDes shall be performed at the following frequencies:
a.
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecu-tive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously obst'ved degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
b.
If the results of the inservice inspection of a steam gen-erator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specifica-tion 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.
c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.
2.
A seismic occurrence greater than the Operating Basis Earthquake.
3.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
4.
A main steam line or feedwater line break.
TROJ AN-UNIT 1 3/44-8
LCA 26, Revision 1 Page 13 of 37 REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in the Specification:
1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
Degraded Tube means a tube containing imperfections >20%
of the nominal wall thickness caused by degradation.-
4.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeos the plugging limit. A tube containing a defect l
is defective.
6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to (40)% of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the colo leg.
TROJAN-UNIT 1 3/4 4-9
LCA 26, Revision 1 Page 14 of 37 REACTOR C0OLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 9.
Preservice Inspection means an inspection of the full length of each tube in eacn steam generator performed by eddy current techniques prior to service establish a baseline canaition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.
4.4.5.5 Reports a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
b.
The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the perioo l
in which the inspection was completed.
This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identif':ation of tubes plugged.
c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
TRa]AN-UNIT 1 3/4 4-9a
LCA 26, Revision 1 Page 15 of 37 REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 com-porents shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY:
ALL MODES ACTION:
a.
With the structu.al integrity of any ASME Code Class 1 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) price to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations, or comply with ACTION item d below.
b.
With the structural integrity of any ASME Code Class 2 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F, or comply with ACTION item d below.
c.
With the structural integrity of any ASME Code Class 3 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service, or comply with ACTION item d below.
d.
If the requiremerits of the above ACTION items are not met, in lieu of the requirements of Specification 3.0.3, an evaluation can be performed to determine the consequences of continuing to operate with reduced structural integrity or with a temporary repair made to the affected component (s),
or be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
e.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.10.1 ASME Code Class 1, 2, and 3 components shall be inspected in accordance with the requirements of Specification 4.0.5.
In addition, each reactor coolant pump flywheel shall be inspected per tne recommenda-tions of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
TROJ AN-UNIT 1 3/4 4-29
LCA 26, Revision 1 Page 16 of 37 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that the following valves are in the indicated position with power to the operators removed:
Valve Number Yalve Function Valve Position a.
M0 8806 a.
RWST Isolation a.
open*
b.
M0 8812 b.
RHR Suction b.
open*
c.
M0 8835 c.
SIS Cold Leg Injection c.
open*
d.
M0 8002-A d.
SIS Hot Leg Injection d.
closed e.
MO 8802-B e.
SIS Hot leg Injection e.
closed f.
M0 8703 f.
RHR Hog Leg Discharge f.
closed g.
M0 8809-A g.
RHR Cold Leg Discharge g.
open*
h.
M0 8809-8 h.
RHR Cold. Leg Discharge h.
open*
1.
M0 8811-A 1.
closed *
- j. F0 8811-8 j.
closed
- k.
M0 8813 k.
SI Pump Mini-flow isolation k.
open*
1.
M0 8814 1.
SI Pump Mini-flow isolation 1.
open*
b.
At least once per 31 days on a STAGGERED TEST BASIS by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in its correct posi ti on.
- Power to be restored and valves operated from within control room for switchgear from injection to recirculation mode following LOCA.
TROJAN-UNIT 1 3/45-4
LCA 26, Revision 1 Page 17 of 37 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
By visual inspection which verifies that no loose debris l
(rags, trash, clothing, etc.) is present in the containment wnich could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing containment integrity, and 2.
Of the areas affected within containment at the completion of each containment entry when containment integrity is established.
d.
At least once per 18 months by:
l 1.
Verifying automatic isolation of the RHR system frc.n the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
2.
A visual inspection of the containment sump and verifying that the subrystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
3.
Verifying the correct position of each of the following ECCS manual throttle valves:
a) Cold-Leg High-Pressure Boron Injcction System Valve Numbers 8810A through D.
b) Cold-Leg Safety Injection System Valve Numbers 8822A through D.
c) Hot-Leg Safety Injection System Valve Numbers 8816A through D.
TROJAN-UNIT 1 3/4 5-5
LCA 26, Revision 1 attachment 1 Page 18 of 37 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
At least once per 18 months, during shutdown, by:
I 1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.
2.
Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:
a) Centrifugal charging pump.
b)
Safety 1.njection pump.
c) Residual heat removal pemp.
3.
Verifying that on a RWST--Low signal the residual heat removal pumps are automatically de-energized.
f.
Following the completion of ECCS modifications that alter system I
flow characteristics by performing a flow balance test to verify the following injection flow rates:
1.
Cold-Leg High-Pressure Boron Injection System Each Injection Leg = 117 (+0, -5) gpm - Single Pump Operation 2.
Cold-Leg Safety Injection System Each Injection Leg = 158 (+5) gpm - Single Pump Operation 3.
Hot-Leg Safety Injection System Each Injection Leg = 325 (+0, -5) gpm - Applicable Pump Operation with Train Isolation TROJAN-UNIT 1 3/4 5-6
LCA 26, Revision 1 Page 19 of 37 EMERGENCY CORE COOLING SYSTI'.S SURVEILLANCE REQUIREMENTS (Continued) g.
Within four hours following completion of each valve l
stroking operation or maintenance on the valve when the subject ECCS is required to be OPERABLE by verifying the correct position of each of the following ECCS manual throttle valves:
1.
Cold-Leg High-Pressure Boron Injection System Valve Numbers 8810A through D.
2.
Cold-Leg Safety Injection System Valve Numbers 8822A through D.
3.
Hot-Leg Safety Injection System Valve Numbers 8816A through D.
h.
By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1.
Centrifugal charging pump
)2400 psig 2.
Safety irjection pump
>1455 psig 3.
>165 psig TROJAN-UNIT 1 3/4 5-6a
LCA 26, Revision 1 Page 20 of 37 CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray system: shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one containment ; pray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstated OPERABLE:
a.
By verifying that on recirculation test line flow, each pump develops a discharge pressure of >228 psig at a flow of >586 gpm for FE-2066 and >227 psig at a flow of >592 gpm for7E-2067 when tested pursiiant to Specification 470.5.
TROJAN-UNIT 1 3/5 6-10
LCA 26, Revision 1 Page 21 of 37 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Verifying that each valve (manual, power operated or auto-l matic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
c.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a containment spray test signal.
2.
Verifying that each spray pump starts automatically on l
a containment spray test signal.
3.
Verifying that on a RWST--Low-Low signal the spray pumps l
are automatically de-energized.
d.
At least once per 5 years by performing an air or smoke flow l
test through each spray header and verifying each spray nozzle is unobstructed.
TROJAN-UNIT 1 3/4 6-11
LCA 26, Revision 1 Page 22 of 37 CONTAINMENT SYSTEMS SPRAY ADDITIVE SYSTEM LIMITING CONDITION FOR OPERAT10N 3.6.2.2 The spray additive system shall be OPERABLE with:
a.
A spray additive tank containing at least 3000 gallons of not less than 30 percent by weight Na0H solution, and b.
Two spray additive eductors each capable of adding Na0H solution from the chemical additive tank to a containment spray system pump flow.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the spray additive system inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the spray additive syst's to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The spray additive system shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 6 months:
1.
Verifying the solution level in the tank, and 2.
Verifying the concentration of the NaOH solution by chemical analysis.
TROJAN-UNIT 1 3/4 6-12
LCA 26, Revision 1 Page 23 of 37 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS c.
At least once per 18 months, during shutdown, by verifying l
that each automatic valve in the flow path actuates to its correct position on a containment spray test signal.
d.
At least once per 5 years by verifying a water flow rate of 37 + 3 gpm from the spray additive tank to each containment spray system with the spray pump operating in the recirculation mode through the test line.
TROJAN-UNIT 1 3/4 6-13
LCA 26, Revision 1 Page 24 of 37 CONTAINMENT SYSTEMS 3/4.E.3 CONTAli; MENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) specifiea in Table 3.6-1 inoperable, either:
a.
Restore the Inoperable valve (s) to CPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demon-strated OPERABLE prior to returning the valve to service af ter maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
TROJAN-UNIT 1 3/4 6-15
LCA 26, Revision 1 Page 25 of 37 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 sha11 be demon-strated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position.
b.
Verifying that on a Containment Ventilation isolation signal, each Purge and Exhaust valve actuates to its isolation position.
4.6.4.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall bc determined to be within its limit when tested pursuant to Specification 4.0.5.
TROJAN-UNIT 1 3/4 6-16
LCA 26, Revision 1 Page 26 of 37 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, b.
With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-2; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
TRGJAN-UNIT 1 3/4 7-1
TABLE 4.7-1
$8 STEAM LINE SAFETY VALVES PER LOOP E
h VALVE NUMBER LIFT SETTING (+2%, -3%)
ORIFICE SIZE l
[
A, Q
{
R a.
PSV-2211, PSV-2231, PSV-2251, PSV-2271 1170 psig Q = 11.05 sq. inches b.
PSV-2212, PSV-2232, PSV-2252, PSV-2272 1200 psig Q = 11.05 sq. inches c.
PSV-2213, PSV-2233, PSV-2253, PSV-2273 1210 psig R = 16.0 sq. inches d.
PSV-2214, PSV-2234, PSV-2254. PSV-2274 1220 psig R = 16.0 sq. inches e.
PSV-2215, PSV-2235, PSV-2255, PSV-2275 1230 psig R = 16.0 sq. inches T'+
20*
OfE ue 0~h E
a
LCA 26, Revision 1 Page 28 of 37 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.
2.
Verifying that each pump starts automatically upon l
receipt of a safety injection test signal.
4.7.1.2.2 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying the fuel level in its day tank, 2.
Verifying that a sample of diesel fuel from its fuel tank is within the acceptable limits specified in Table 1 of ASTM 0975-68 when checked for viscosity, water and sediment, and 3.
Verifying the diesel starts from amutent condition and operates for > 15 minutes.
b.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to a inspection in accordance with procedures prepared in conjunction with its manufacturer's recomendations for this class of standby service, and 2.
Verifying the diesel and pump operate for > 60 minutes.
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LCA 26, Revision 1 Page 29 of 37 4
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equip-ment actuates to its correct position on a safety injection signal.
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LCA 26, Revision 1 Page 30 of 37 e
PLANT SYSTEMS This page left intentionally blank.
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LCA 26, Revision 1 Page 31 of 37 PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent service water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety-related equipment that is not locked, sealed, or odierwise secured in position, is in its correct position.
b.
At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety-related equip-ment actuates to its correct position on a safety injection signal.
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LCA 26, Revision 1 Page 32 of 37 PLANT SYSTEMS This page left intentionally blank.
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LCA 26, Revision 1 Pace 33 of 37 APPLICABILITY A
BASES 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
This clarification is provided to ensure consistency in sur-veillance intervals throughout these Technical Specifications ana to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification, the more restrictive require-ments of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Adaenda.
For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Yessel Coce provision which allows pumps to be tested up to one week after return to normal operation. And for example, the Technical Specification defini-tion of OPERABLE does not grant a grace period before a cevice that is not capable of performing its specified function is ceclared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code pecvision which allows a valve to be incapable of performing its speci-fied function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being ceclared inoperable.
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LCA 26, Revision 1 Page 34 of 37 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.
With one reactor coolant loop not in operation, THERMAL POWER is restricted to < 35 percent of RATED THERMAL POWER until the Overtemperature AT trip is reset.
Either action ensures that the DNBR will be maintained above 1.30.
A loss of flow in two loops will cause a reactor trip if operating above P-7 (10 percent of ' RATED THERMAL POWER) while a loss of flow in one loop will cause a reactor trip if operating above P-8 (35 percent of RATED THERMAL POWER).
A single reactor coolant loop provides sufficient heat removal capability for removing core decay heat while in HOT STANDBY:
- however, single failure considerations require placing a RHR loop into operation in the shutdown cooling mode if component repairs and/or corrective actions cannot be made within the allowable out-of-service time.
3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.
Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam at 1107, of the valve's setpoint.
The relief capacity of a single safety valve is adequate to relieve any overpressurize condition which could occur during l
shutdown.
In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.
During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.
The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.
Demonstration of the safety valves' lift settings will occur only during shutdown and will be perfonned in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
l TROJ AN-UNIT 1 B 3/4 4-1
LCA 26, Revision 1 Page 35 of 37 REACTOR COOLANT SYSTEM BASES 3/4.4.5 STEAM GENERATORS CONTINUED system and the secondary coolant system (primary-to-seconcary leakage =
500 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated l
that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with the all volatile treatment ( AVT) of secondary coolant.
However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging will be required of all tubes with imperfections exceeding the plugging limit which, by the definition of Specification 4.4.5.4.a is 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the l
original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.
These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolunt Pressure Boundary Leakage Detection Systems," May 1973.
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LCA 26, Revision 1 Page 36 of 37 REACTOR COOLANT SYSTEM
~
BASES The actual shift in NDTT of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTM E185-73, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.
Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel.
The heatup and cooldown curves must be recalculated when the ARTNDT determined from the surveillance capsule is different from the calculated ARTNDT for the equivalent capsule radiation exposure.
The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature require-ments of Appendix G to 10 CFR 50.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4-3 to assure compliance with the requirements of Appendix H to 1G CFR Part 50.
The limitations imposed on pressurizer heatup and cooldown and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.
3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).
Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code,1971 Edition and Addenda tnrough winter 1972.
All areas scheduled for volumetric examination have been pre-service mapped using equipment, techniques and procedures anticipated for use during post-operation examinations.
To assure that consideration is given to the use of new or improved inspection equipment, techniques and procedures, the Inservice Inspection Program will be periodically reviewed on a 40 month basis.
l TROJAN-UNIT 1 B 3/4 4-9
LCA 26, Revision 1 v
Page 37 of 37 REACTOR COOLANT SYSTEM BASES The use of conventional nondestructive, direct visual and remote visual test techniques can be applied to the inspection of most reactor coolant loop components except the reactor vessel.
The reactor vessel requires special consideration because of the radiation levels and the requirement for remote underwater accessibility.
The 29-in. Reactor Coolant System piping requires special ultrasonic technique because it is centrifugally cast austenitic steel.
The techniques anticipated for inservice inspection include visual inspections, ultrasonic, radiographic, magnetic particle and dye pene-trant testing of selected parts.
For normal opening and reclosing, the structural integrity of the Reactor Coolant System is unchanged. Therefore, satisfactory per-formance of a system leak test at 2235 psig following each opening and subsequent reclosing is acceptable demonstration of the system's struc-tural integrity.
These leak tests will be conducted within the pressure-temperature limitations for Inservice Leak and Hyorostatic Testing and Figure 3.4-2.
ASME 2 and 3 components will be pressure tested at least once toward the end of each inspection interval (10 years). Pressure test criteria for Class 2 components are defined in ASME XI, Article IWC-5000; pres-sure test criteria for Class 3 components are defined in ASME XI, Article IWD-5000.
The hydraulic pipe snubbers are designed to restrict the amount of pipe motion which would occur in the event of a seismic event.
Verification of proper hydraulic fluid level on the reservoirs of these pipe snubbers ensures that the snubbers will perform their intended functi on.
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