ML20112K119
| ML20112K119 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/21/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20112K122 | List: |
| References | |
| DPR-50-A-106 NUDOCS 8504090345 | |
| Download: ML20112K119 (17) | |
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o UNITED STATES h p)y> v.(;
g NUCLEAR REGULATORY COMMISSION
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU l.0 CLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION,IINIT NO. 1 e
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. OPR-50 1.
The Nuclear Re9ulatory Comission (the Commission) has found that:
A. The application for amendment by GPU Nuclear Corporation, et al (the licensees) dated June 8, 1981, as superseded February 17, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulatioris set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
'D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the phblic; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
0504090345 850321 PDR ADOCK 05000289 P
. 2.
Accordingly, the license is amended'by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(21 of. Facility Operating Licerse No. OPR-50 is h,ereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE FUCLEAR REGUI.ATORY C0FMISSION g
/t JohnF.Stolz, Chief O p rating Reactors Branch #4 J vision of Licensing
Attachment:
Chances to the Technical Specifications Oate of Issuance: l! arch 21,1985 N
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ATTACHMINT TO LICE. AMEN 0 MENT NO.106 FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace the followinh pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert vi vi
.vii vii
_ 63 3-63 3-64 thru 3-79 3-64 4-60 4-60 4-61 4-61 4-62 4-62 4-63 4-64 4-65 4-66 4-67 Fig. 4.17-1 6-21 6-21 N
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LIST OF TA31IS TABLE TITLE PACE 1.2 Frequency Notation 1-8 2.3-1 Reactor Prot ction System Trip Setting Limits 2-9 3.1.6.1 Pressure Isolation Check Valves Between the Primary 3-15a Coolant System and LPIS 3.5-1 Instruments Operating Conditions 3-29 3.5-2 1ccident Monitoring Instruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d
[
3-87 3.18-1 Fire Detection Instruments 3.21-1 Radioactive Liquid Effluent Monitoring Instrumentatics 3-97 ~
3.21-2 Radioactive Liquid Effluent Monitoring Instrumentatics 3-101 3-122 3.23-1 Radiological Environmental Monitoring Program 3-126 3.23-2 Reporting Levels for Radioactivity Concentration in Invironmental Samples i
4-3 4.1-1 Instrument Surveillance Requirements 4-8 4.1-2 Minimum Iquipment Test Frequency 4-9 4.1-3 Minimum Sampli$g Frequency 4.1-4 PostAccidentNonito-ingInstrume=tation 4-103
^
4.2-2 Surveillance Capsules Insertion and Withdrawal Schedule 4-27a 4-84 4.19-1 Minimus Number of Steam Generators to be Inspected Daring Inservice Inspection
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4-85 4.19-2 Steam Generator Tube Inspection 4-88 4.21-1 Radioactive Liquid Effluent Monitoring g
Instrumentation Surveillance Requirements 4-91 4.21-2 Radioactive Caseous Effluent Monitoring
. Instrumentation Surveillance Requirements 4-98 4.22-1 Radioactive Liquid Waste Sampling & Analysis Program Radioactive CaseousIWaste Sampling & Analysis Program 4-106 4.22-2 4.23-1 Maximum valves for the Lover Limits of Dectaction (LL3).
4-118 Amandaane 59,7;, JM.106 vi
^ ? ~ ^. ~ T LIST OF FIGURES Ficure Title 2.1-1 TMI-l Core Protecticrk Safety ' Limit 2.1-2 TMI-1 Core Prote:r. ion Safety Limits 2.1-3 THI-l Core Prote:: tion Safety Bases 2.3-1 TMI-l Protection System Maximum Allowable Set Points
-2.3-2 '
Protection System Maximum Allowable Set Points for Reactor Power Imbalance, TMI-l 3.1-1 Reactor Coolant System Heat-up/Cooldown Limitations (Applicable to 5 EFPY) 3.1-2 Reactor Coolant System, Inservice Leak and Hydrostatic Test Limitations _(Applicable to 5 EFPY) 3.1-3 Limiting Pressure vs. Temperature Curve for 100 STO cc/ Liter HO 2
3.5-2A Rod Position Limits for A Pump Operation Frcm 0 to 125 1 5 EFPD, TMI-l 3.5-29 Rod Position Limits for A Pump Operation from 125 g 5 EFPD, TMI-l 3.5-20 Red Position Limits for 2 and 3 Pump Operation from 125 1 5 EFPD to EDC, TMI-l 3.5-2E Power Irrealance Envelope for Operation from 0 EFPD to EOC 3.5-2F Deleted 3.5-2G LOCA Limited Maximun Allowable Linear Heat - TMI-l 3.5-2H APSR Position Limits for Operation from 0 EFPD to EOC 3.5-1 Incore Instrumentation Specification A/ial Imbalance Indication TMI-l 3.5-2 Incore Instrumentation Scecification Racial Flux Tilt Indication TMI-l 3.5-3 Incore Instrumentation Specification 4.17-1 Snubber Functional Test - Sample Plan 2 5-1 Extended Plot Plan TMI
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vii Amendment No. II, 17, 27, 77, Q, N JP, B,106 x
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3.16 SHOCK SUPPRESSORS (SNUB 8ERS)
LIMITING CONDITION FOR OP 9 ATION 3.16.1 Each safety related snubber shall be OPERASLE.
APPLICABILITY:
Whenever the system protected by the snubber is required to be OPERASLE.
ACTION:
With orie or more snubbers incperable, within 72 hcurs replace or restore the inoperable snubber (s) to CFERABLE status and perform.an engineering evaluation per Specification 4.17.1.g.2 on the attached component or declare the attached
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system inoperable and follow the appropriate action statement for that system.
BASES Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of an incperable snubbdr (Jue to failure to activate (lockup) is an increase in the probability of stlu:tural dan. age to piping as a result of a seismic or other event initieting dynamic loads. The consequence of snubber inoperability due to failure to extend or retract is an increase in the prcbability of structural damage to piping as a result of thermal motion. It is therefore required that all snubbers required to protect the primary coolant system or any other safeiy system or component which is required to be operable must also be operable. During plant conditions other than cperating, snubbers on those
_ systems that are recuired to be operable during that plant condition are also required to be coerable.
3-63 Amendment No. 30.106
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r INTENTICNALLY BLANK PAGES 3-64 through 3-79 Amendment No. 30, fl, $/,
.p 105
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~4.17 SHOCK SUPPRESSORS (SNLESERS)
SURVEILLANCE RE0'JIREMENTS 4.17.1 Each snubber shall be. demonstrated OPERABLE by performance of the following inspection program.
.a.
Insoection Tyoes As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inscections Snubbers are categorized as inaccessible or. accessible during reactor operation and may be treated independently. The inaccessibility of each snubber determined to be inaccessible shall be reviewed and approved by the TMI-l Radiological Controls Manager' or.an authorized designee. The determination shall be based upon the'then existing radiation levels in each snubber location and the expected time to perform the visual inspection and shall be in accordance with the recommendations of Regulatory Guides 8.8 and 8.10.
Snubbers accessible during reactor cperation shall be inspected in accordance with the schedule stated below. Snubbers inaccessible during reactor operation shall be inspected during each reactor shutdown greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> where access is restored
- unless previously inspected in accordance with the schedule stated below.
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Visual inspections shall include all safety related snubbers and shall be performed in accordance with the following schedule:
No. Inoperable Snubbers of each Subsequent Visual type Der Insoection Period Insoection Period **#
0 18 months + 25%
1 12 months T 25%
2 6 months 7 25%
3, 4 124 days 125%
5,6,7 62 days
+ 25%
8 or more 31 days
- 25%
- Snubbers may continue to be inaccessible during reactor shutdown greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (e.g. if purging of the reactor building is not permitted).
- The inspection interval for each type of snubber shall not be lengthened more than one step at a time tnless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step' the first time and two steps thereafter if no ' inoperable snubbers of that type are found.
- The provisions of Table 1.2 are not applicable.
4-60 AmendmentNo./@,106
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' SHOCK SUPPRESSORS (SNUBBERS)
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SURVEILLANCE REQUIREMENTS (Continued) c.
Refuelino Outace Insoections t At least once each refueling cycle during shutdown, a visual inspection shall be performed of all safety related snubbers attached to sections of safety systems piping that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems.
d.
Visual Insoection Acceptance Criteria Visual inspections shall verify: (1) that there are no visible
't indications of damage or impaired operability and (2) attachments to the foundation or supporting structure are secure. Snubbers which -
appear inoperable as a result of visual inspections may be determined CPERABLE for the purpose of establishing the next visual
-inspection interval, provided that:
(1) the cause of the rejection e
is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.17-1f.
When the reservoir outlet port of a snubber is found to be uncovered by fluid, the snubber shall only be declared operable if functional testing in both extention and retraction directions is satisfactory and an engineering evaluation concludes that this snubber is operable.
e.
Functional Tests
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At least o'nce each refueling cycle during shutdown, a representative sample of snubbers shall be tested using one of the following sample
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plans.
The sample plan shall be selected prior to the test period i
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 p
prior test period shall be used:
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- 1) At least 10% of the total of each type of snubber in use in the plant shall be functionally tested either in-place or in a bench test. For each snubber of a type that coes not meet the functional test acceptance criteria of Specification 4.17.lf, an additional 10% of that type of snubber shall be functionally tested'until no more failures are found or until all snubbers of that type have been functionally tested; or C
D i 4-61 Amencment No. /$, 106 e
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SHOCK SUPPRESSORS (SNLBBERS)
SURVEILLANCE PECUIREMENTS (Continued)
- 2) A representative sample of each type of snubber shall be functionally tested in accordance with Figure 4.17-1.
"C" is the total number of snubbers of a type found not meeting the acceptance. requirements of Specification 4.17.lf..The ct.rnulative number of snubbers of a type tested is denoted by "N".
At the end of each cay's testing, the new values of "N" and "C" (previous day's total plus current day's increments) shall be plotted on Figure 4.17-1.
If at any time the point plotted falls in the " Reject" region all snubbers of that type shall be functionally tested. If at any time the point plotted falls in the " Accept" region testing of that type of snuober may g
be terminated. When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the
" Reject" region, or all the snubbers of that type have been tested. Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time, provided all snubbers tested with the failed equipment during the day of equipment failure are ratested.
The representative sample selected for 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 practicable that they are representative of the various configurations, operating environments, and the range of size and capacity of snubbers of each type. Snubcers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be
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included in the sample plan. If, during the functional test, additional sampling is required due to failure of only one type of snubber, the functional test results shall be reviewed at that time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
f.
Functional Test Acceotance Criteria The snubber functional test shall verify that:
- 1) Snubber activation (restraining action or lockup) is achieved within the specified velocity range in both tension and compression.
- 2) Snubber release rate (bleed) is achieved in both tension and L
compression, within the specified range.
- 3) Fasteners for attactraent of the snubber to the component and to the snubber anchorage,are secure.
4-62 Arendment No. % 106 4
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SHOCK SUPPRESSORS (SNUBSERS)
SURVEILLANCE REOUIREMENTS (Continuad)
Testing methods may be used t' measure parameters indirectly, or o
parameters other than those specified, if those results can be correlated to the specified parameters through established methods.
g.
Functional Test Failure Analvsis~
1.
Cause of Failure Evaluation An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The results of this evaluation shall be used, i
if applicable, in selecting snubbers to be tested in an effort to determine the operability of other snubbers, irrespective of -
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type, which may be subject to the same failure mode.
2.
Damace Evaluation For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.
If any snubber selected for functional testing either fails to activate (lockup) or fails to extend or retract, i.e.,
frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type which are subject to the same defect shall be evaluated in a manner to ensure operability. This testing requirement shall be independent of the requirements stated in Specification 4.17.le for snubbers not meeting the functional test acceotance criteria, h.
Functional Testing of Recaired and Reciaced Snubbers
. Snubbers which fail the visual inspecticn or the functional test acceptance criteria shall be repaired cr replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test result shall have been tested to meet the functional test criteria before installation in the unit.
4-63 Amendment No. 106
SHOCK SUPPRESSORS (SNU39ERS)
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SURVEILLANCE REQUIREMENTS (Ccotinued) 1.
Snubber Seal Reclacement Procram A snubbe seal replacement program shall be developed whereby the seal service life of hydraulic snubbers is monitored to ensure that the service life is not exceeded between surveillance inspections.
The maximum expected service life for the various seals shall be established based on engineering information. The seals shall be replaced so that the maximum expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. The seal replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.
The program shall be fully implemented by startup following cycle 7 refueling.
4 4-64 Amendment No. 106
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i-Bases All safety related hydraulic snubbers are visually inspected for overall integrity and cperability. The inspection includes verification of proper orientation, adequate hydraulic fluid level, and proper attachment of snubber to piping and structures.
The visual-inspecticn frequency is based upon maintaining a constant level of
' snubber protection. Thus, the required inspection interval varies inversely c
with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to i
lengthen the required inspection interval. Any inspection whose results 4
require a shorter inspection interval will override the previous schedule.
Those snubbers which are inaccessible during reactor cperation are not required to be inspected in accordance with the indicated inspection interval but must be inspected during the next shutdown when access is restored.
. hen the cause of the rejection of a snubber by visual inspection is clearly W
established and remedied for that snubber and for any other snubbers that may be generically susceptible, that snubber may be exempted from being counted as inoperable if it is determined cperable by functional testing. Generically susceptible snubbers are those snubbers which are of a specific make or cccel and have the same design features directly related to rejection of the snubbers by visual inspection, or are similiarly located or expcsed to the same environmental conditions such as temperature, radiation, ard viaration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubbar mode of failure, in order to
' determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mcde of failure has imparted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, one of the two sampling and acceptance criteria methods are used:
1.
Functionally test 10% of a type of snubber with an acciticnal 1C%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.17-1.
Figure 4.17-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J.
Duncan.
e 5
4-65 Amendment No. 106 i
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Snubber seal service life'is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records. The requirement to monitor the snubber seal service life is included to ensure that the seals periodically undergo a performance evaluation in view.of,their. age and cperating conditions. These records will provide statistical bases 'for future consideration of snubber seal service life.' The requirements for the maintenance of records and the snubber seal service life are not intended to affect plant operation.
A technique and method for functional testing of the 550,000 lb. reactor coolant pump snubbers is currently under development.. The functional test program shall be submitted for NRC approval by cycle 6 refueling.
As a ba' sis for permanent deletion of a snubber from the list of safety related snubbers, an engineering analysis must be performed to verify that the original safety analysis design criteria are either met or exceeded. Snubber i
additions and deletions are reported to the NRC in accordance with 10 CFR 50.59 requirements.
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4-66 Amendment No.
106
.F Pages 4-67 through 4-71 INTENTIONALLY ELANK Arrendment No.106 4
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10 20 30 40 50 60 70 80 90 10C-5 N
CUMULATIVE NO. OF SNUBBERS OF TYPE TESTED l
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FIGURE 4.17-1 l
SNUBBER FUNCTIONAL TEST - SAMPLE PLAN 2 I
Amendment No. 106 v.
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Records of the service. lives of all safety related hydraulic snubbers including the date at which the service life commences and
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associated installation and maintenance reccrds.
n.
Records for Environmental gualification which are covered under the provision of paragrsph 6.15.
6.11 RADIATION PROTECTICN PROGRAM Procedures for persennel radiation protecticn shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6_.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by
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paragraph 20.203(c)(2) of 10 CFR 20:
a.
Each High-Radiation Area shall be barricaded and censpicucusly posted as a High Radiation Area, and personnel desiring entrance shall obtain a Radiaticn Work Permit (Rh?). Any individual entering a High Radiation Area shall (a) use a centinuously indicating dose rate monitoring device or (b) use a radiation dose rate integrating
~ device which alarms at a pre-set dose level, or (c) assure that a radiological control technician provides periodic radiatien surveillance with a dose rate monitoring instrument.
b.
Any. area accessible to personnel where a major portion of the body could receive in any cne hcur a dcse in excess of cne thousand crem shall be Iceked or guarded to prevent ~unautnorized entry. Tne keys to these locked barricades shall be maintained under the administrative control of the Radiological Controls Foreman on duty.
The Radiation Work Permit is not required by Radiclogical Controls persennel during the performance of their assigned radiaticn prctection duties provided they are follcwing radiolcgical centrol prececures fer entry into High Radiation Areas.
6.13 PPOCESS CONTROL PROGRAM (PC3) 6.13.1 The PCP shall be approved by the Cce.missicn prior to imolementation.
6.13.2 GoU Nuclear Ccrcoration initiated cnanges to the PCP:
1.
Shall be submitted to the NRC in the Seniannual Radicactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:
a.
sufficiently detailed info:matien to justify the changes without benefit of additional or sucalemental infornation; I
.1 b.
a determination t' hat the changes di:: not reduce the overall conformance of tne solidified waste product to existing criteria for sclid wastes; anc 6-21 Amend ent No.11, 33, Z J7.' 106
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