ML20012F030
| ML20012F030 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/26/1990 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012F031 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9004090327 | |
| Download: ML20012F030 (7) | |
Text
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UNiit o ST ATES y ',.r < /[
- NUCLE AR REGULATORY COMMIS$10N
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Q DOCKET.N0. 50 341 FERM1 2 i
AMENDP.ENT TO FACILITY OPERATING LICENSE Ainendment No. 52 License No. NFF.43 l
1.
Ttt 1.'uclear Regulatory Cor.niission (the Commissien) has found that l
A.
The application for amendrent by the Cetroit Edison Company (the lictr.ste) dated December 22, 1988 as surplenentec May 10, 1989, i
con. plies with the standaros and requiretrents of the Atcric Erergy Act of 15$4, as an. ended (the Act), and the Corritsien's rules anc regulations set forth in 10 CFR Chapter It C.
The facility will cperate in conformity with the application, the provisions cf the Act, and the rules ar.d regulatior;5 of the Coraissicnt C.
There is reasonable assurance (i) that,the activities euthorized by this arer.drent can be conducted withnut erdangering the Fealth ar.d t
safety cf the public, and (ii) that such act1vities will te conducted in con.pliarce with the Con.n.ission's regulaticris; i
D.
The issuance of this anier.drient will t'et be inin'ical to the corrion defense and security or to the health and $6fety of the public; and E.
Tte issuance of this ertndnent is in accerdance with 10 CFR Part 51 of
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the Cctritsion's rcsulations and all applicable requirer.ents h6ve beer satisfied.
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Accordirigly, the license is amended by changes to the Technical Specifica.
I tiers er ir.dicated in the attachment to this license amendr.ent and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to i
rttd as follt-ws:
Technical Specificatior4 and Environnental_ Protection Plan i
The Technical Specific 6tions contained in Appendix A, as revised through Anet.dnent No. 52, and the Environmental Protection Plan centained in i
Appendix B, are hereby incorporated in the license. DECO shall cperate the facility in accordance with the Technical Specificaticos and the Enviror.n.e.ntal Protection Plan.
9004090327 900326 ADOCK 0500 1
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This license anendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY C0lHI$$10N j
hn 0. Thoma, Actin!) Director i
Project Directorate.!!.1 Division of Reactor Projects - !!!,
i IV, V & Special Projects Office of Nuclear Reactor Regulation i
Attachment:
f Changes to the Technical Specifications Date of Issuance: March 26, 1990 i
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ATTApr.ENT To t! CENSE AMENpkET_ NO._'d ELjiY,0![RATINGL!cENSEN0,NPF-43 T
DOCKET NO. 50 341 l
I Peplace the following pages of the Appendix *A" Technical $pecifications with I
the attached rages. The revised pages are identified by Amendrent nurter and l
centain a vertical line indicating the area of change.
The correspor. ding l
overitaf rages are also provided to r.aintain docunent completer,ess.
I REMOVE INSERT 3/4 0-3 3/4 0 3 B 3/4 0-3 B 3/4 0 3 3/4 4 25 3/4 4-25 3/4 4-26*
3/4 4 26' l
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FMeFliial page provided to n.aintain docun<ent completeness, flo changes ccr,taired in these pages, i
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SURVElltANCEFEQUIREMENTS_(gotinued)
A5ME Boiler and pressure Yessel Required frequencies Code and applicable Addence for performing inservice terminology for inservice inspection and testing i
inspection and testing activities activities i
Weekly At Itast once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days l
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 j
c.
The provisions of Specification 4.0.2 are applicable to the above i
reeuired frequthcies for performing inservice inspection and testing activities.
d.
Performance of the abcve inservice inspection and testing activities I
shall be in aedition to other specified Surveillance Requirements.
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Nothing in the ASME Boiler and Pressure Vessel Code shall be i
construea to supersede the requirenents of any Technical Specification.
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The Inservice Inspection (NCE) Program for piping " identified in i
NRC Generic Letter SS 01. dated January 25, 1988, NRC position on IGSCC in EWR Austenitic Stainless Steel Piping" le, methods and shall be performed in accordance with the staff positions on schedu personnel, and sample expansion included in this generic letter.
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i FERMI - LiNIT 2 3/4 0 3 Amendment No. 31,52
c' APPLICABILITY BA$t$
4.0.5 This specification ensures that inservice inspection of AMSE Code Class 1, 2 and 3 components and inservice testing of A$ME Code Class 1, 2 and 3 pumps and valves of will be performed in accordance with a periodically updated version of Section XI of the A$ME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50. Section 50.554 Relief from any of the above requirements has been provided in writing by the Comission and is not a part of these Technical Specifications.
This specification includes a clarification of the frequencies of performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and pressure Code and applicable Addenda. This clarification 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 restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
For example, the surveillance activities prior to entry into an OPERATIONAL CONDITION or other specified applicability concition takes precedence over the ASME Boiler and Pressure Yessel Code provision which allows pumps to be tested up to one week after return to normal operation.
And for example, the Technical Specification 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 provision which allows a valve to be incapable of performing its specified 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 declared inoperable.
NRC Generic Letter 88 01 identified NRC's position on intergranular stress corrosion cracking (IGSCC) in BWR Stainless Steel weldments.
This letter establishes requirements to inspect these weldments to a special schedule and by procedures, personnel and equipment that are qualified under a formal program approved by the NRC.
FERMI - UNIT 2 B 3/4 0-3 Amendment No. 52
R{ACTM COOLANT SYST[M
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}]4,.4MTRt'CitrRAL INTEGRITY tIMIT!WG CONDITION FOR OPERATION 3.4.8 The structural integrity of A$MC Code Class 1, 2, and 3 components shall te p.aintained in accordance with Specification 4.4.6.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.
ACTION:
a.
WiththestructuralintegrityofanyASMECodeClass1corponent(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 more than 50'F above the minimum temperature required by NDT considerations, b.
Vith the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirerhents, restore the structural integrity of the affected compenent(s) to within its limit or isolate the affected component (s) prior to increasing the reactor coolant i
system temperature above 200'F.
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With the structural integrity of any ASME Code Class 3 component (s) i not conforming to the above requirements, restore the structural i
integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
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The provisions of Specification 3.0.4 are not applicable.
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5tMEILLECE REQUIREMEN15 I
4.4.8 I;c requirements other than Specification 4.0.5.
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l FERMI - UNIT 2 3/4 4-25 Amendment No. 52
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i REACT 0L C00LANT $Y} TEM 3 44 & 9 PE5ftUAE HEAT REMOVAL h0T $HUTDOVN QMITINGCOWDIT10WFOROPERATION 3.4.9.1 Twoi shutdown cooling mode loops of the residual beat removal (RHR) system shall be OPERABLE and, at least one recirculation pump shall be in operation or, at least one shutdown cooling mode loop shall be in operation *H with each loop consisting of at least:
a.
One OPERABLE RHR heat exchanger.
APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than tr.e RNR Cul-in Dermissive setpoint.
ACTION:
4.
With less than the abcve required RHR shutdown cooling mode loops CFERACLE, irurediately initiate corrective action to return the required loeps to OPERABLE status as seen as possible. Within I hour ard at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify the OFERABIL!fY of at least one alternate method cap 6ble of decay heat removal for each inoperable RHR shutdown cooling mode loop.
Be in at least COLD SHUT 00WN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.**
b.
With r.either a recirculation pump ner an PHR shutdown cooling mode loop in operation, immediately initiate corrective action to return either at least one recirculation purp pr at least one RHR shutdown c0011ng mode loop to operation as socn as oossible. Within I hour t
esteblish reactor ecolant circulation by an alterrate nethod and I
monitor reactor coolant temperature and pressure at least once per hour.
c.
The provisions of $pecification 3.0.4 are not applicable for up to l
A hours for the purpose of establishing the RHR system in the shut-i down cooling mode once the reactor vessel pressure is less than the i
RHR cut-in permissive setpoint.
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SURVEILLANCE REOUIRD#ENTS
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4.4.9.1.1 At least one shutdown cooling mcde loop of the residual trat renoval i
system or at least one recirculation purp shall be determined to be in operation i
and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- 0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing.
'The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 tcur period.
- The RHR shutdown cooling mode loop may be removed from operation during tydrcstatic testing.
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- Wherever both RHR shutdown cooling mode loops are inoperable if unable to t
attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant l
l teraperature et lcw as practical ty use of alternate heat rerovel r'ethocs.
l FERMI - UNIT 2 3/4 4-2f-