ML102810483
| ML102810483 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/28/2010 |
| From: | Detroit Edison |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML102810483 (19) | |
Text
DETROIT EDISON - FERMI 2 AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST 09/28/10 To: 00935 US NRC PAGE 1 DOCUMENT CNTRL DESK WASHINGTON, DC 20555 Media: 8 1/2 X 11 Number Cnt Issue DTC Doc. Serial Number Page Rev Copies Lvl Date Sec Status TMTRM TRM VOL I 99 1 IR 09/27/10 AFC Please destroy or mark all revised, superseded, or cancelled documents as such. CONTROLLED stamps must be voided by lining through and initialing.
Detroit Edison EF2, C/O Info Mgmt 140 NOC, 6400 North Dixie Highway, Newport MI 48166. (734) 586-4338 OR (734) 586-4061 for questions or concerns.
Ref: u05875
LICENSING DOCUMENT TRANSMITTAL FERMI 2 TECHNICAL REQUIREMENTS MANUAL - VOL I Revision 99 dated 09/27/10 Immediately, upon receipt of the item(s) below, please insert and/or remove the pages indicated.
Destroy the removed pages. Be sure that Revision 98 has been inserted prior to inserting these pages.
Location Remove Insert . '
In Front of TRM Manual Title Page Rev 98 05/24/10 Title Page Rev 99 09/27/10 Immediately following List of Effective Pages List of Effective Pages Title Page LEP-1 through LEP-4 Rev 98 05/24/10 LEP-1 through LEP4 Rev 99 09/27/1.0 Table of Contents TRM-iii Rev 98 05/10 TRM-iii Rev 99 09/10. -
3.12 Fire Protection Page.TRM 3.12-4 Rev 98 05/10 Page TRM.3.12-4 Revý99 09/10 5 Administrative Cowtrols "ag6eTRMS5.0"a Rev 93 03/09 Page.TRM.5.0-aRev,99.09.10 .
Page'TRM 5.0-1 Rev 31 10/99 Page TRM 5.0-l"Rev 99 09/10 Page TRM 5.0-2 Rev 31 10/99 Page TRM 5.0-2 Rev 99 09/10 Page TRM 5.0-ý3 Rev 31 10/99 Page TRM 5.0-3 Rev 99 09/10 Page-TRM 5.0-4 Rev 31 10/99 Page.TRM 5.0-4.Rev 99 09/10 Page TRM 5.0-5 Rev.31 10/99 Page TRM 5.0-5 Rev 99 09/10 . .
Page TRM 5.0-6 Rev 31 10/99 Page TRM 5.0-6 Rev 99 09/10 Page TRM 5.0-7 Rev 31 10/99 Page TRM 5.0-7 Rev 99 09/10 Page TRM 5.0-8 Rev 93 03/09 Page TRM 5.0-8 Rev 99 09/10 Page TRM 5.0-9 Rev 31 10/99 NONE B3.7 Plant Systems Page TRMB3.7.7-1 Rev 91 08/08 Page TRMB3.7.7-1 Rev 99 09/10.
END
C, Fermi 2 Technical Requirements Manual Volume I Detroit Edison ARMS- INFORMATION DTC: TMTRM File: 1754 DSN: TRM VOL-I Rev: 99 Date 09/27/10 Recipient Of g3
J FERMI 2 - TECENICAL REQUIREMENTS MPANUAL VOL I LIST OF EFFECTIVE PAGES Page Revision Page . Revision TRE i Revision 76 TRE 3.3-31 Revision 31 TRM ii Revision 73 'TRM 3.3-32 Revision 31 TRM iii Revision TRE 3.3-33 93 Revision 31 TRM iv Revision 76 TRM 3.3-34 Revision 31 TRM V Revision 79 TRE 3.3-35 Revision 60 TRM vi Revision 31 TRM 3.3-36 Revision 41 TRM 1.0-a Revision 31 TRE 3.3-37 Revision 72 TEN 1.0-1 Revision 31 TRM 3.3-38 Revision 31 TRM 2.0-1 Revision 31 TRM 3.3-39 Revision 31 TRE 3.0-a Revision 31 TRM 3.3-40 Revision 56 TRM 3.0-1 Revision 63 TRM 3.3-41 Revision 56 TRM 3.0-2 Revision 72 TRM 3.3-42 Revision 45 TRM 3.0-3 Revision 54 TRE 3.3-43 Revision 62 TRM 3.0-4 Revision 72 TRM 3.3-44 Revision 72 TRM 3.1-a Revision 31 TRE 3.3-45 Revision 31 TRE 3.1-1 Revision 31 TRE 3.3-46 Revision 31 TRM 3.2-1 Revision 31 TRM 3.3-47 Revision 31 TRM 3.3-a Revision 31 TRm 3.3-48 Revisio6n 31 TRM 3.3-b Revision 31 TMN 3.3-49 Reiii ibn 31 TRM 3.3-c Revision 31 TEM 3.4-a Rervions .31 TRM 3.3-d Revision 31 TRM 3.4-1 Revision,36 TRM 3.3-1 Revision 34 TRM 3.4-la Revigion.71 3.3-2 Revision 59 TRH 3.4-lb Revioin,71 TRM TEN 3.3-3 Revision 31 TRM 3.4-2 Re&iCion -31 TRXg TRM 3.3-4 Revision 31 TRE 3.4-3 Revision 31 TRM TRM 3.3-5 Revision 31 TRE 3.4-4 Revidi6n,31 TRM 3.3-6 TEN Revision 31 TRM 3.4-5 Revision',31 3.3-7 Revision 31 TRE 3.4-6 Revision'31 3.3-8 Revision 31 TRM 3,4-7 Revision*31 3.3-9 Revision 31 TAM 3.4-8 Reirision 31 3.3-10 Revision 31 TEM 3.4-9 Revision'31 TRL* 3.3-11 Revision 31 TEM 3.4-10
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TRM TRN 3.3-16 Revision 31 TEN, 3.6-4 Revision.55 TEN 3.3-17 Revision 31 TRM 3.6-5 Revision 87 TRM 3.3-18 Revision 52 TRM 3.6-6 Revision 33 TEN 3.3-19 Revision 31 TRM 3.6-7 Revision 31 TRE TEN 3.3-20 Revision 31 TRE 3.6-8 Revision:31 TRM TEN TEN 3.3-21 Revision 59 TRM 3.6-9 Revision 85 3.3-22 Revision 31 TRE 3.6-10 Revision 31 3.3-23 Revision 31 TRM 3.6-11 Revision.31 3.3-24 Revision 31 TRN 3.6-12 Revision 31 3.3-25 Revision 31 TRE 3.6-13 Revision 71 TRM TEN TE TRM 3.3-26 Revision 31 TRM .3.6-14 Revision 31 3.3-27. Revision 31 TRM 3.6-15 Revision 31 3.3-28 Revision 76 TRN 3.6-16 Revision 31.
3.3-29 Revision 76 TRE 3.6-17 Revision 31 3.3-30 Revision 31 TRM 3.6-1.8 Revision 33.
TRM Vol. I LEP-1 REV 99 09/27/10
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.. .. RM 3.6-29 Revision 31 TRM 3.9-4 Revision 88 TEM 3.6-30 Revision 31 TRM 3.9-5 Revision 31 TRX 3.6-31 Revision 31 TRM 3.10-1 Revision31
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TRE 3.8-9 Revision 50 TRM 5.0-1 Revision 99
- TRE 3.8-10 Revision 50 TRE 5.0-2. Revision 99 3.8-11 Revision 50 TRM 5.0-3 Revision 99 3.8-12 Revision 31 TRM 5.0-4 Revision 99 TRM Vol. I LEP-2 IREV 99 09/27/10
FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I LIST OF EFFECTIVE PAGES Page Revision Page Revision TRM 5.0-5 Revision §9 TRM B3.4.7-1 Revision 31 TRM 5.0-6 Revision 99 TRM B3.5-1 Revision 31 TRM 5.0-7 Revision 99 TRM B3.6.1-1 Revision 31 TRM 5.0-8 Revision 99 TRM B3.6.2-1 Revision 67 TRM. B1.0-I Revision 31 TRM B3.6.3-1 TRM B2. 0-1 Revision 87 TRM B3.0-1 Revision 31 TRM B3.6.4-1 Revision 31 TRM B3.0-2 Revision 63 TRM B3.6.5-1 Revision 31 TRM B3.0-2a Revision 63 TRM B3.6.6-1 Revision 70 Revision 72 TRM B3.6.7-I Revision 31 TRM B3.0-2b Revision 72 TRM B3.6.8-1 Revision 31 TRM B3.0-2c Revision 72 TRM B3.7.1 Revision 31
. TRM B3.0-3 Revision 31 TRM B3.7.2-1 Revision 31' S TNRM B3.0-4 Revision 31 TRM B3.7.3-1 Revision 73-TRM B3.0-5 Revision 54 TRM B3.7.4-1' Revision 31
. TRM B3.0-6 Revision'72 TRM B3.7.4-2. Revision 31.
S.' TRM 33.0-7 -Revision 72 TRM -B3.7.5-1. . Revision. 31.'
TRM B3.1-1 'Revision. 31 TRME:S3.7.6-1
'Revision. 32 TRM.B3.7.7-1'"
."" TRM B3.2-1 Revision 31" 'Revisiobn 99".
- .' . ". TRM B3.3.1-1:. :Revision 31 TRM"B3.7.8-1
" ."'... ,.TRM B3.3.1-2 .,Revision 31 T.RM 33.7.9-2.7 ReVision. 79 .
.......... ,....TRM B3.3.2-2 :.Revision 31 -, TRM-B3.8.2'-I- - Rd3`1i6n 31.'
TRM B3.3.3-1 Revision 67 TEN B3.8.3-1 Redvigion 96 TRE B3.3.4-1: ,.*Revision 31 -- TEN 33.8.4-i Revi'sion 31:'
TRM B3.3.4-2 Revision 84
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. TRE B3.3.8-1 -Revision 31 TRM B3.12.4-1 Revision 31 TRM B3.3.9-1 Revision 31 ETRH
-B3.12.5-1 Revision 31
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... TRM B3.3.11-1 Revision 45 TRM.'B3.12.7-1
" - TRM B3.3.12-1 Revision 31 Revision 62 TRM 33.12.8 *. TRM B3.3.13-1 Revision 31 TRM B3.3.14-1 Revision 31
". TRE B3.4.1-1 Revision 31 TRM B3.4.1-2 Revision 71 TRM 33.4.1-3 Revision 71
. TAM B3.4.T-4 Revision 71 TRM B3.4.1-5 Revision 71 TEN B3.4.2-1 Revision 31 TRM B3.4.3-1' Revision 31 TRM B3.4.4-1 Revision 31 TRM B3.4.5 Revision 31 TRM B3.4.6-1 Revision 31 TEN Vol. I LEP-3 REV 99 09/27/10
FERMI 2 - TECHNICAL REQUXRME16ETS NVUMA VOL I LIST OF EFFECTIVE PA~GES CORE OPERATING LIMXTS REPORT COLR 14, Revision I Page Revision Notation Page
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.1 TRM Vol. I LEP-4 TREV 99 09/27/10
FERMI 2 - TECHNICA.L REQUIREMENTS XANUAL VOL I Table of Contents (Cont'd)
Section and Title Page TR 3.9 REFUELING OPERATIONS TR 3.9.1 Communications ................................... TRM 3.9-1 TR 3.9.2 Refueling Platform ................................ TRM 3.9-2 TR 3.9.3 Crane Travel - Spent Fuel Storage Pool ............ TRM 3.9-4 TR 3.9.4 Reactor Pressure Vessel Water Level - Refueling TRM 3.9-5 TR 3.10 SPECIAL OPERATIONS (Blank) ........................... TRM 3.10-1 TR 3.11 RADIOACTIVE EFFLUENTS TR 3.11.1 Temporary Outdoor Storage Tank Radioactivity. TRM 3.11-1 TR 3.12 . FIRE PROTECTION TR 3.12.1 Fire Detection Instrumentation ..................... TRM 3.12-1 TR. 3.12.:2 Fire Suppression Water System .................... TRX 3.12-8 TR 3.12.3 Spray and Sprinkler Systems ........ ............... TRM 3.12-13 TR 3.12.A CO 2 Systems ........................................... TRM 3.12-16 TR 3.12.5 Halon Systems .................................. .... TRM 3.12-18
- TR. 3.12.6 Fire Hose Stations ................................... *TRM 3.12-20 TR 3.12.7 Yard Fire.Hydrants and Hydrant Hose Houses ..... . TRM 3.12-26 TR 3.12.8 Fire Rated Assemblies ............................ ... TRM 3.12-29 V. R 4.0 DESIGN FEATURES (Blank) .................... ........ ....... TRM4.0-1
- TR- 5.0 ADMINISTRATIVE CONTROLS TR 5.1 Programs TRM- 5.0-1
.,TR Inservice Inspection and Testing .Program:for Snubbers TR 5.1.2: Configuration Risk Management Program (Blank)-. TRM 5.0-7.
TR 5.2 Reports TR 5.2.1 Startup Reports .............................. .........
- TRM 5.0-8 BASES TR B1.0 USE AND APPLICATION TR BI. I Definitions (Blank) ......................... ...... TRM B1.0-1 TR B2.0 SAFETY LIMITS (SLs) (Blank) ......................... TRM B2.0-1 TR B3 .0 Limiting Condition for Operation (TRLCO)
Applicability .................................. ...... TRM B3.0-1 -
TR B3.0 Surveillance Requirement (TRSR) Applicability'....... TRM B3'. 0-3.
REACTIVITY CONTROL SYSTEMS
.TR B3.1 TR B3.1.1 Control Rod Drive Housing Support ................ TRM B3. 1-1 TR B3.2 POWER DISTRIBUTION LIMITS (Blank) .................... TRM B3.2-1 (continued)
TRM VOL I I TRM-iii REV 99 09/10
Fire Detection Instrumentation TR 3.12.1 TABLE TR3.12.1-1 (Page 1 of 3)
Fire Detection Instrumentation FIRE TOTAL NUMBER OF INSTRUMENTS'A' DETECTIO IONIZATION PHOTOELECTRIC THERMAL INFRARED FUNCTION N ZONE (X/Y) (X/Y) (X/Y) (X/Y)
- 1. Reactor Building'h)
- a. Torus area 1 810.
- b. NW corner rooms 4/0 RHR pump
- e. NE corner rooms 5. 5/0 RCIC
- f. First.floor 31/0 8/0
- g. EECW system area 10 2i/o second floor
- h. Third floor 15 23/0 I.
- i. Fourth floor 2:7 22/0 2/0 J. Refueling area,. 17 1/0 : :."1010 fifth floor
- 2. Auxiliary Building
- a. Basement N 4 610 control air equipment
- b. Corridors, 5 210 210 562 ft, 563 ft
- c. First floor 6 17/0 mezzanine cable tray, 583 ft.
603 ft
- d. Switchgear room, 9 10/0 corridor area second floor
- e. -cable tunnel 9 10/0 (continued)
(a) (X/Y) X is number of Function A (early-warning fire detection and notification only) instruments.
Y is number of Function B (actuation of fire suppression system and early warning and notification) instruments.
(b) The fire detection instruments located within the containment are pot required to-be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
TRM Vol. I TRM 3.12-4 REV 99 09/10
SECTION 5.0 DETAILED INDEX OF SECTION Page TR 5.1.1 Inservice Inspection ana Testing Program for Snubbers .......................................... TRM 5.0-1 (Program for TR 3.7.9)
TR 5.1.2 Configuration Risk Management Program .............. TRM 5.0-7 (CRMP Program) (Blank)
TR 5.2.1 Startup Reports ...................................
(Reporting Requirements)
TRM 5.0-8 I REV. 99 09/10 TRM Vol.
TEN Vol. II TRM 5.0-a TEN 5 a REV. 99 09/10
Programs TR 5.1 TR 5.0 ADMINISTRATIVE CONTROLS TR 5.1 Programs TR 5.1.1 Inservice Inspection and Testing Program for Snubbers The Snubber Program specified in TR 5.1.1 implements the requirements of the ASME OM Code, Subsection ISTA and ISTD, 2004 Edition, as allowed by 10CFR50.55a(b) (3)(v) in lieu of ASME Section XI, IWF-5200(a) and (b) and IWF-5300(a) and (b). This'program applies to preservice and inservice examination and testing requirements.
- a. Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer,.irrespective of._
capacity.
b.. Visual Inspections Visual examination of snubbers shall satisfy the requirements:
of ISTD-4000 for all:preservice and inservice examinations.-..-
Snubbers are categorized as 'inaccessible or accessible during.--.
reactor-operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by ISTD Table 4252-1. The visual j.
inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4252-i. '
The first inspection interval determined using this criteria.-
shall be based upon the previous inspection interval. When the prerequisites, of Code Case OMN-13 have been satisfied, the examination interval may be extended as allowed by the Code Case.
- c. Visual Inspection Acceptance Criteria Visual Inspection shall verify that (1) there are no visible indications of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional:
All program snubbers'are to be inspected using the VT-3 examination methodology described in ASME Section XI, IWA-2213, 2001 Edition with 2003 Addenda. If a snubber does not meet the examination requirements; an evaluation shall be performed to determine the cause of the unacceptability.
Snubbers which appear inoperable as a result of 'visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Inservice Inspection and Testing Program for SnUbbers, TR 5.1.1 Section f: and (continued)
TR~4. 5.0-1 REV 99 09/10 TRM Vol. I Vol. I TRM. 5. 0-1 REV 99 09/10
Programs TR 5.1 TR 5.0 ADMINISTRATIVE CONTROLS TR 5.1 Programs C. Visual Inspection Acceptance Criteria (continued)
(2)the test demonstrates that the unacceptable condition did not affect operational readiness of the snubber. For those snubbers common to more than one system, the OPERABILITY of such snubbers shall be considered in assessing the OPERABILITY of each of the related systems. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and appropriate actions taken.
- d. Transient IEvent Inspection A visual examination shall be performed of all hydraulic and "
mechanical snubbers attached to sections of systems that have' experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible areas anda6 months .for inaccessible areas following such an event. In additi6ri to satisfying the.visual inspection*-
acceptance criteria, freedom-of-movement of mechanical snubbers shall-be verified using at least one of the-.
following.; (1). st+/-oking; or (2) testing. Any resultant corrective action taken'due to such a transient shall be
'considered'independent of'ISTD-:4100, ISTD-4200, ISTD-5200, .
ISTD-5300, ISTD-5400.or ISTD-5500.
- e. Functional' Tests Functional testing of snubbers shall satisfy the requirements of ISTD-5000 for all preservice and inservice testing.
During the first refueling shutdown and at least once per fuel cycle thereafter during shutdown, a representative sample of snubbers ,shall be either in-place or bench tested using-one of the sample plans described below. Snubber testing may begin no earlier than 60 days before a scheduled refueling outage. Snubbers in parallel or multiple installation shall'be identified and counted individually.
The sample plan shall be selected prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior-test shall be implemented:
(continued)
TRM Vol.I TRM 5.0-2 REV 99 09/10
Programs TR 5.1 TR 5.1 Programs
- e. Functional Tests (continued)
- 1. 10% sample plan - At least 10% of the total snubbers from each Design Test Plan Group, (DTPG) shall be functionally tested in accordance with ISTD-5300. Fractional sample sizes shall be rounded up to the next integer. For each snubber from a DTPG that does not meet the functional test acceptance criteria of the Inservice. Inspection and Testing Program for Snubbers, TR 5.1.1 Section f, an additional 5% of that type of snubber shall be functionally tested from that DTPG. Testing is completed when-the mathematical expressions of ISTD-5331 are satisfied, or all snubbers in the DTPG or Failure Mode Group (FMG) have been tested. Additional snubber testing is not required for isolated functional failures. An isolated functional test failure is a failure that does not cause other snubbers to.be suspect; or
.2. .37 sample test plan- An initial sample of 37 snubbers
- shall be selected raendomly from each 37 plan snubber DTPG.'
"o . *-and shall be functionally tested in accordance with ISTD-5400 and Figure ISTD-5431-1. "'C" is the total number of
. requirements of the inservice Inspection.and Testing Program.for Snubbers, TR 5.1.1 Section f The cumulative'.
. number of snvbbers tested from each DTPG .is denoted by.'
. For edch snubber from a DTPG that does not meet the
" -'. functional test acceptance criteria -of Secti6n f, an
- additional sample equal to 18 or 19 snubbers -from that DTPG shall be functionally tested. Testing is complete when the mathematical expressions of ISTD-5431 are satisfied, or all snubbers in the DTPG or FMG have been tested. Additional snubber testing is not required for isolated functional failures. An isolated functional test failure is a fai'lure that does .not cause other snubbers to-be suspect..
(continued)
RSV 99 09/10 V61. II TRM Vol.
T~iM TRM 5.0-3 TRM 5.073 REV 99 09/10
Programs TR 5.1 TR 5.0 ADMINISTRATIVE CONTROLS TR 5.1 Programs
- e. Functional Tests (continued)
- 3. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type.and reviewed before beginning the testing.
The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubber of each type. . Snubbers placed in the same locations as snubbers which failed the previous functional test shall be retested at the time of the next Functional test shall not be included in the sample plan.. If during the but I..
functional testing, additional sampling is required due to snubber test failure, the functional testing results shall.
be reviewed at the time to determine additional testing requirements in accordance with ISTD-5300, and ISTD-5400.
The unacceptbile'snubbers may be categorized into failure mode group(s) in accordance with ISTD-5314, ISTD-5320 or
.-ISTD-5420.. A failure mode group shall include all unacceptable snubbers.that. have 'a given failure mode and:
S
- -all other snubbers subject 'to the saie failure mode.- once.
.... a failure mode group has been established,' it can be separated for continued testing apart from the general-population of. snubbers-..
~f. Functional. Test,-Acceptance Criteria The snubber functional test shall verify that:
- 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tensi'onand compression; 2.' Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range;
- 3. For mechanical snubbers, the drag force required to maintain motion of the snubber is within the specified range in both directions of travel; and
- 4. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.
Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
(continued)
TRM Vol. I TRM 5.0-4 REV 99 09/10
Programs TR 5.1 0 TR 5.1 Programs
- g. Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. If a design deficiency in a snubber is found, it shall be corrected by appropriate means. The results of this evaluation shall be used, as applicable, to determine Failure Mode Groups (FMG's) in accordance with ISTD-5270, and in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject'to the same failure mode. Snubbers deleted from the plant based on analysis of the affected piping system shall nevertheless be considered..
in its respective examination population, examination category, or .FMG for determining the corrective action.'
For snubbers found inoperable, an engineering evaluation shall beperformedon the components to which the inoperable:--
snubbers are attached. The purpose of 'this engineering
- evaluation shall be .to determine if the components to which.vý;".
.the inoperable "snubbersare attached were adversely affected:...
by the inroperability.of the snubbers in order to ensure .that. "
- ~s~ervice.
the-component'remains capable of meeting'the designed D'
If any snubber'selected for functional testing either fails'."
to. lock up pr~fails to move,' i.e., frozen-in-place, the cause will' be evalulted..and 'if caused by manufacturer or design'- .
deficiency all snubbers of the same type subject to the same defect shall be tested, repaired, modified or replaced in.
accordance with ISTD-1600. Snubbers of the same type subject.
to the same defect shall be categorized as one failure mode group for the purpose of additional testing.
- h. Functional Testing of Repaired and-Replaced Snubbers.
Snubbers which fail the visual inspection or the functional test acceptance criteria shall be adjusted, repaired, modified or replaced and satisfy the Repair Replacement requirements of ASME Section XI as applicable. Replacement or modified.snubbers shall have a demonstrated suitability for the application and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance .
criteria subsequent to their most recent service before being I installed in the unit.
I TRM 5.0-5 (continued).
Vol.- II TRM Vol. TRM 5.0-5 REV 99 09/10
Programs TR 5.1 TR 5.0 ADMINISTRATIVE CONTROLS TR 5.1 Programs
- i. Snubber Service Life Program I The service life of hydraulic and mechanical snubbers shall be monitored in accordance with ISTD-6000, to ensure that the service life is not exceeded between surveillance inspections. -The maximum expected service life for various seals, springs, and other critical parts shall be determined and predicted based on manufacturer and engineering -
information and shall be extended or shortened based on monitored test results and failure history. Critical parts -..
shall be replaced so that the maximum service life will not -
be exceeded during a period when the snubber is required to"'.,
be OPERABLE. The parts replacement shall be documented and..
the documentation shall be retained. Cause evaluations. of any snubber-test failures shall be used to determine if an adjustment to the'.expected service" life *is `4equirec. Testing of additional snubbers is'not required based upon 'the- results of snubbers tested specifically for service life monitoring, purposes. . .. . -. "
0 TRM Vol. I TRM 5.0-6 REV 99 09/10
Programs TR 5.1 TR 5.1 Programs TR 5.1.2 Configuration Risk Management Program THIS PAGE INTENTIONALLY LEFT BLANK-I REV 99 09/10 I
.TRM TflM Vol.-
Vol. II TRM 5.0-7 TRM 5.0-7 REV 99 09/10.1
Reports TR 5.2 TR 5.0 ADMINISTRATIVE CONTROLS TR 5.2 Reports In addition to the applicable reporting requirements. of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.
TR 5.2.1 Startup Report
- a. A summary report of plant startup and power escalation testing shall be submitted following.:
- 1. Receipt of an Operating License';
- 2. Amendment to the license involving a planned increase in power level;
- 3. Installation of fuel that has a different design or has. been..
manufactured by a different fuel supplier; and
- 4. Modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
- b. The startup report shall address each of the tests identified in Subsection 14.1.4.8 of the Final Safety Analysis'Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test.
program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
- c. Startup reports shall be submitted within:
- 1. 90 days following completion of the startup test program;
- 2. 90 days following resumption or commencement of commercial power operation; or
- 3. 9 months following initial criticality, whichever is earliest.
If the startup report does not cover all three events (i.e.,
initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.
TEN 5.0-8 REV 99 09/10 1 FERMI UNIT 2 TEN UNIT 2 TRM TRM 5.0-8 . REV 99 09/10 1
Appendix R Alternative Shutdown Auxiliary Systems TR B3.7.7 TR B3.7 PLANT SYSTEMS TR B3.7.7 Appendix R Alternative Shutdown Auxiliary Systems BASES The-systems identified in this section are those utilized for Appendix R Alternative shutdown but not included in other sections of the Technical-Specifications and Technical Requirements Manual. The ACTION statements assure that the auxiliary systems will be OPERABLE or that acceptable alternative means are established to achieve the same objective.
There are four independent Combustion Turbine-Generator units onsite. CTG ii Unit 1 has a diesel engine starter and thus can be. started independently from offsite power. CTG 11 Units 2, 3, and 4 have AC-motor starters and rely on a 480-volt AC feed. The phrase "alternative source power", as used in .TRM Specification 3.7.7, Required Action C.2.2, is defined as a source of power that is not reliant on offsite power for starting (if required) or operating (if already running) and capable of supplying the required loads on the 4160-volt busses associated with the Alternative Shutdown System.
One of the two installed Standby Feedwater Pumps and one of. the two. listed Drywell Cooling Units are'necessary for Appendix R Alternative shutdown. The Division 1 EECW system operates in support of the drywell cooling function. The nitrogen bottles associated with the Division 1 EECW makeup.tank support the operation of this makeup tank during, a dedicated shutdown fire until ,the -
procedural actions necessary to enable the automatic makeup capability have been completed. Therefore unlimited operýation with one of the two- components inoperable is justified provided increased surveillance is performed on the components which remain OPERABLE.
The SBFW pump performs a function for Appendix..R Alternative..Shitdown analogous to RCIC for Remote Shutdown. As such the SBFW Surveillance Requirements are patterned after RCIC Surveillance Requirements, including the flow: test. capacity requirement. The specified flow value includes an allowance for normal instrument tolerance above the minimum flow required for adequate core cooling.
The controls for CTG 11 Unit 1, the Standby Feedwater Pumps, and-Drywell. Cooling Units 1 and 2 are only required when the respective equipment is OPERABLE. The.
power supplies for BOP Battery Chargers 2C-1 and 2CI-2 are required.to support OPERABILITY of the respective control circuits.
I.