Proposed Tech Specs Revising Spent Fuel Storage Capacity, to Permit Installation of Sufficient Rack Modules to Bring Spent Fuel Storage Capacity Up to Original Design ValueML19327A821 |
Person / Time |
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Site: |
Hope Creek ![PSEG icon.png](/w/images/c/cc/PSEG_icon.png) |
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Issue date: |
10/11/1989 |
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From: |
Public Service Enterprise Group |
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To: |
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Shared Package |
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ML19327A820 |
List: |
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References |
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LCR-89-17, NUDOCS 8910180196 |
Download: ML19327A821 (8) |
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Category:TECHNICAL SPECIFICATIONS
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Qualifications of Operations Manager ML18101B3831996-05-22022 May 1996 Proposed Tech Specs,Requesting Approval of Changes to QA Program 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. Corrections Are Considered to Be Administrative in Nature ML20196L1231999-05-17017 May 1999 Proposed Tech Specs Pages,Revising TS to Include Oscillation Power Range Monitor (OPRM) Sys ML20206T8941999-05-12012 May 1999 Revised Event Classification Guide,Including Rev 12 to Table of Contents,Rev 8 to Attachment 8,Rev 8 to Attachment 7 & Rev 8 to Attachment 9 ML20206G2111999-04-30030 April 1999 Proposed Tech Specs,Incorporating Programmatic Controls in Tech Specs for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20206G2281999-03-31031 March 1999 Rev 18 to ODCM for Hope Creek Generating Station ML20205E8101999-03-29029 March 1999 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20204J2871999-03-22022 March 1999 Proposed Tech Specs Bases Page B 3/4 8-1d,correcting Editorial Errors ML20204J1291999-03-22022 March 1999 Proposed Tech Specs Bases Pages B 3/4 8-1,B 3/4 8-1a, B 3/4 8-1b,B 3/4 8-1c & B 3/4 8-1d,correcting Editorial Errors That Occurred During Implementation of Hope Creek License Amends 100 & 101 ML20202B6171999-01-19019 January 1999 Revised TS Bases 3/4.6.1.1,revised to Clarify When Verification of Primary Containment Integrity May Be Performed by Administrative Means ML20198T0281998-12-30030 December 1998 Proposed Tech Specs Re Changes to Flood Protection TS LCO & Associated Action Statements ML20198N3981998-12-28028 December 1998 Proposed Tech Specs Permitting Increase in Allowable Leak Rate for MSIVs & Deleting MSIV Sealing Sys ML20198C9641998-12-16016 December 1998 Proposed Tech Specs Pages,Replacing Accelerated Testing Requirements of TS Table 4.8.1.1.2-1 with EDG Performance Monitoring & Deleting TS 4.8.1.1.3 Requirement to Submit 30- Day Special Rept for Diesel Failures ML20155D3591998-10-22022 October 1998 Proposed Tech Specs Page for Amend to License NPF-57, Establishing More Appropriate Minimum Battery Electrolyte Temperature Limits ML20154R5871998-10-19019 October 1998 Proposed Tech Specs Section 3.0.4,eliminating Restrictions for Filtration,Recirculation & Ventilation Sys During Fuel Movement & Core Alteration Activities ML20154L5021998-10-0808 October 1998 Revised Tech Spec Page,Which Corrects Editorial Errors ML20151X7321998-09-0808 September 1998 Proposed Tech Specs Permitting Use of non-class 1E Single Cell Battery Chargers,With Proper Electrical Isolation,For Charging Connected Cells in Operable Class 1E Batteries ML20151S4331998-08-25025 August 1998 Proposed Tech Specs,Implementing Appropriately Conservative SLMCPR for Upcoming Cycle 9 Plant Core & Fuel Designs ML20236F1171998-06-25025 June 1998 Proposed Tech Specs Deleting Requirement to Perform in-situ Functional Testing of ADS Valves Once Every 18 Months as Part of Startup Testing Activities ML20249A8181998-06-12012 June 1998 Proposed Tech Specs Re Increased Operational Flexibility During Periods of Elevated River Water Temp & Maintain Ultimate Heat Sink Operation within Design ML20247K7381998-05-13013 May 1998 Proposed Tech Specs Page Re Change to Inservice Leak & Hydrostatic Testing Requirements ML20216B0641998-05-0101 May 1998 Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page ML20217P9351998-04-28028 April 1998 Proposed Tech Specs Section 3/4.4.2,implementing More Appropriate SRV Setpoint Tolerances ML20216F4541998-03-0606 March 1998 Proposed TS Section 4.2.2 Re Terrestrial Ecology Monitoring ML18106A8281998-03-0404 March 1998 Rev 1 to Reactivity Manipulations Documentation Guide. ML20197H5941997-12-19019 December 1997 Proposed Tech Specs Pages,Revising TS Section 4.2.2, Terrestrial Ecology Monitoring, by Changing Wording to Include Completion of Salt Drift Monitoring Program ML20197H8511997-12-0808 December 1997 Rev 0 to IST Program Submittal Interval 2,Dec 21,1997 Through Dec 20,2006 ML20198J6431997-10-10010 October 1997 Rev 0 to 55-WP3/F43TB3-05, Weld Procedure ML20211M6121997-10-0707 October 1997 Cycle 4 Startup Physics Testing ML20211M2401997-10-0303 October 1997 Proposed Tech Specs Pages Associated W/Slmcpr Changes ML20217D3761997-09-29029 September 1997 Proposed Tech Specs Adding Requirement to Perform Weekly Sampling & Monthly & Quarterly Composite Analyses of Ssws When Racs Is Contaminated ML20211F6201997-09-24024 September 1997 Proposed Tech Specs Section 3/4.5.1,adding Surveillance Requirement to Perform Monthly Valve Position Verification for Each of Four Residual Heat Removal cross-tie-valves ML20198H2471997-08-26026 August 1997 Proposed Tech Specs Implementing Conservative Safety Limit Min Critical Power Ratio for Plant Cycle 7 Core & Fuel Designs ML20217Q6731997-08-26026 August 1997 Proposed Tech Specs,Requesting Rev to TS to Clarify Plant Basis for Compliance W/Frvs TS Requirements ML20211M2641997-08-26026 August 1997 Revised TS Bases Pages for Amend 101 to License NPF-57 ML20217Q3081997-08-25025 August 1997 Proposed Tech Specs Re Ultimate Heat Sink Temp & River Water Level Limits ML20198J6541997-08-20020 August 1997 Rev 3 to 55-PQ7001-03, Procedure Qualification Record ML20198J6501997-08-20020 August 1997 Rev 5 to WP3/F43TB3-05, Welding Procedure Specification ML20210P3471997-08-20020 August 1997 Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling Outage ML20149G4301997-07-16016 July 1997 Proposed Tech Specs Implementing Appropriately Conservative Safety Limit Min Critical Power Ratio ML20211M2531997-07-16016 July 1997 Sanitized Version of TS Page Changes Re SLMCPR ML20141C1621997-06-19019 June 1997 Proposed Tech Specs Revising Sections of TSs to Delete Reference to Rod Sequence Control Sys & to Reduce Rod Worth Minimizer Low Power Setpoint from 20% to 10% ML20140D2201997-05-30030 May 1997 Proposed Tech Specs,Providing marked-up Pages to Address NRC Reviewer Comments ML20141G8291997-05-19019 May 1997 Proposed Tech Specs Revising Ultimate Heat Sink Temp & River Water Level Limits Which Resolve TS Issues Related Issues Documented in Hope Creek Corrective Action Program ML20137N6271997-04-0101 April 1997 Proposed Tech Specs 4.6.1.1, Primary Containment Integrity, TS 3/4.6.1.2, Primary Containment Leakage, TS 3/4.6.1.3, Primary Containment Air Locks & TS 4.6.1.5.1, Primary Containment Structural Integrity ML20137M1331997-03-31031 March 1997 Proposed Tech Specs Revising TS to Improve Consistency Between TS & Plant Configuration,Operation & Testing & Completing Required CA to Resolve Discrepancies Identified in CA Program 1999-09-30
[Table view] |
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i PROPOSED CRANGE '!O THE TECHNICAL SPECIFICATIONS
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FACILITY OPERATING LICENSE NPF-57 NOPE CREEK GENERATING STATION
- DOCKET No. 50-354
Reference:
LCR 89-17 DESCRIPTION OF THE CHANGE Revise the spent fuel storage capacity limitation presently stated in Technical Specification, Design Features Section 5.6.3 to read as follows:
I
. "The spent fuel storage pool shall be limited to a storage capacity of no more than 4006 fuel assemblies."
REASON FOR THE CHANGE Technical Specification 5.6.3 presently limits spent fuel storage capacity to 1290 fuel assemblies. This limit was recently raised f rom 1108 assemblies (the installed capacity ht the time that the Operating License and Technical i Specifichtions were issued) by Amendment 27 to the HCGS Facility Operatjug License. That change, as an interim measure, did not increase storene capacity to the plant design limit of 4006 assemblics, but merely provided sufficient i storage capacity to accommodate the third fuel cycle whilo PSE&D r.oup3rsted a
,', reviet of our long-ringn f uel cycle etrht(gy. PSE&G's current lans-range plans involve ;ho htilization of. the semo futi rack design as that of tha origina racks for all future fuel cycles. Therefore, PSE&G is request.ing that TS 5,6.3 .
Le reworded as above to permit the installation of the necessary rack capacity '
for storage of the PSAR design limit of 4006 spent fuel assemblies.
JUSTIFICATION FOR THE CHANGE The criticality, seismic, structural, and thermal / hydraulic analyses remain ;
bounded by the assumptions and calculations (using NRC approved methods) provided in the FSAR. -
- Assuming the use of fuel assemblies with a Kint value equivalent to, or less than the King of a uniformly enriched assembly with 3.4 weight percent U888, the criticality f actor, Ke t t , will remain below 0.95.
- Our reanalysis of design (16 consecutive ref uelings) and maximum (f ull core off-load after 13 consecutive refuelings) spent fuel pool heat loads, using the same NRC approved calculational methods as for previous FSAR analyses, but taking into account our current cycle energy and fuel design projections, demonstrates that our FSAR-analyzed Spent Puel Pool Cooling and Residual Heat Removal Systems' heat removal capabilities of 16.1 x 106 Blu/hr (design) and greater than 45 x 106 Btu /hr (maximum) are adequate for our conservatively calculated design and maximum gpent fuel heat loads of 16.1 x 106 Btu /hr and 34.0 x 106 Btu /hr, respectively
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(as discussed in UFSAR 9.1.3.4). Furthermore, in a recent design change,
, an additional 27 plates have been added to each Spent Fuel Cooling Ileat Exchanger (plate-type exchangers) which raises the design heat removal capability to 19.0 x 106 Btu /hr...providing even greater margins.
- The racks are of the same design and construction as those originally L installed L
- The racks, as passive, free standing, unanchored components that do not interface with, or impact, plant equiment other than the spent fuel pool
< floor remain seismically acceptable.
i 10CFR50.92 SIGNIFICANT NAZARDS CONSIDERATION ANALYSIS PSEfrG has, pursuant to 10CFR50.92, reviewed the proposed amendment to determine whether our request involves a significant hazards consideration.
Criteria 1 The__ operation of liope Creek Generating Station (IICGS) in accordance with the proposed change _will nqt.Jnyo_1y.e e a,significant increase in the probability or conseguencer of,an accident.previously evaluAt h
'Ite proposed aiwendment involvet, ti.e addition of spent luul storage racks that will bring actual spent fuel pool storage capacity into agreetant with the y original f uel storago design. The original r$1R analyses, a'id cur recent l recalcuistione, have verified that, utilizing f uel assemblies with a Kiet value l equivalcut to, or less than, the Knot of a uniformly enriched assembly with 3.4 weicht peretent 08", the criticality factor, Kott, will remain below 0.95.
The current heat removal capabilities of 19.0 x 106 Btu /hr (design) and greater '
than 45 x 106 Dtu/hr (maximum) of the Spent Fuel Pool Cooling and heoidual lleat Removal systems, exceed, with considerable margin, the corresponding design und maximum heat loads of 16.1 x 106 Blu/hr and 34.0 x 106 Btu /hr, as discucced in our Justification for the Change, and are, therefore, adequate for our proposed installation of the original fuel storage design.
Additionally, the racks, which are passive components that do not interface with, or impact, any plant equipment other than the pool iloor, will remain seir.mically acceptable. The existing storage racks, as well as the ones to be added, are !?ee-standing... anchored to neither the fuel pool floor, the pool walls, nor-to adjacent racks.
Based upon the above determination that the criticality, thermal / hydraulic, seismic and structural analyses for our current and future fuel desians, remain bounded by tne assumptions and calculations provided in the FSAR, the proposed TS change, which will increase the maximum spent fuel storage capacity to 4006 assemblies, involves no significant change in the probability or consequences of any accident or malfunction of equipment important to safety previously evaluated in the Final Safety Analysis Report (TSAR).
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Criteria II The operation of Hope Creek Generating Station (HCGS) in accordance with the proposed change will not create the possibility of a new or different kind of accident from any previously evaluated.
The requested change will cause no change to plant equipment, procedures or operating parameters from those originally described in the FSAR. The proposed change will increase the spent fuel storage capacity limit specified in the Design Section of the TS to the original design capacity detailed in the FSAR.
With regard to the installation of the rack modules, which are identical to those presently installed and that are physically oriented the same as in the original plant design described in the FSAR...
The polar crane main hook, the auxiliary geared chain hoist and the rack module lifting fixture, which comprise the Heavy Load Handling System (HLHS), are all designed, inspected and tested to single failure criteria in accordance with NUREG 0544, NUREG 0612, and ANSI 14.6 requirements. The design of all HLHS components incorporate a minimum design safety factor of ten. The polar crane t will be operated only by operators who have been trained in accordance with plant procedures. The polar crane limit switch (North West corner), which normally prohibits polar crane travel over the spent fuel storage area, will be bypassed and the crane bumper will be removed temporarily to allow crane travel over the pool. The safe load path for new rack installation will specifically dVoid movement over aMY preVIOu8ly stored spent f uel in the pool (see the modified UP4AR Figure 9.1 - 37, sheet 4 of 13, attached).
Dypascing of the polic cen9e limit switch and the irssic11ation of the rack !
madelos, utilizing a single failure proof vandling eystem and strict (
actiuittrative centrola, is permissible and discusseu in UTCAR 59.1.5.3.2.6.
The polar crane limit switch will be bypessed only while rack modules are being lifted from the caak washdown area and installed in the pool. Within 7 days prior to, and at least once per 7 days during, the operation of the polar craue for lif ting and installing the rac% modules into the r:a.t fuel pool area, the single-tailure proof HLHS will b6 visually inspected and verified operable with regard to the requirements of Techuical 6pecification (TS) surveillanet 4.9. '. t l Also, for the same time duration, when not actively in service in support of the t installation of the rack modules, the polar crane will be safety-tagged out of service f urther ensuring that only trained operators operate the crane while the travel limits are defeated. Following the termination of the rack module installation, the crane limit switch and bumper will be promptly restored to their original configuration and surveillance testing of the crane interlock and travel stops per TS 4.9.7.1 will be performed to demonstrate that normal limits on crane operation have been restored.
Based upon the above, a postulated heavy load drop over the spent fuel is not considered credible during the installation of the proposed additional rack modules and the possibility of a new or different kind of accident or malfunction of equipment important to safety from any previously evaluated is not created.
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Criteria III The operation of Hope Creek Generating Station (9005) in accordance with the pronosed chance does not involve a sienificant reduction in a marein of saf ety.
The proposed change would permit the installation of racks which are identical I to, and physically oriented the same as, our original plant design. Since the-
< structural, seismic, thermal / hydraulic, and criticality analyses for the L proposed installation of the necessary number of racks to provide our original-design spent fuel storage capability are bounded by our original t assumptions and calculations provided in ySAR Section 9.1.2, the margins of safety will remain essentially unchanged.
Conclusion:
Based upon the above, we have determined that this proposed change does not involve a Significant Hazards Consideration.
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. DESIGN FEATURES 5.6 F'JEL STORAGE l t
i CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
l
- a. A k,ff equivalent to less than or equal to 0.95 when flooded with [
unborated water, including all calculational uncertainties and biases !
as described in Section 9.1.2 of the FSAR. !
- b. A nominal 6.308 inch center to center distance between fuel assemblies I
. placed in the storage racks. ;
5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the [
spent fuel storage racks shall not exceed 0.98 when aqueous foen moderation '
is assumed.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent i inadvertent draining of the poci below elevation 199' 4". (
CAPACITY 3, 5.6.3 The spent fuel storage pool shall be limited to a storage capacity of no more than y fuel assemblies.
4006 ,
S.7 COMP 0NENT CYCLIC OR TPA45!ENT LIMIT I
- 5. 7.1 The components Idrintifie'l in Table 5.7.1-1 are desi ned and shall ce ;
maintained within the cycli~ccrtransientlimitsofTabl6N.7.1-1, 3 l
L HOPE CREEK 5-5
. _ . . - . . . -