ML20126E746
| ML20126E746 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/21/1992 |
| From: | Thayer J YANKEE ATOMIC ELECTRIC CO. |
| To: | Fairtile M NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20126E749 | List: |
| References | |
| BYR-92-112, NUDOCS 9212290300 | |
| Download: ML20126E746 (40) | |
Text
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m 1ANKEE ATOMICELECTRIC COMPANY:
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e December 21, 1992-PC 259 BYR 92-112
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United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Mr. Morton F:irtile Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of. Operating Reactor Support
References:
(a)
License No. DPR 3 (Docket No. 50 29)
(b) letter, M. Fairtile U.S. Nuclear Regulatory i
Commission to J. Grant, Yankee-Atomic Electric-Company, dated August 5.-1992 (c)
Letter, S. Schultz, Yankee Atomic Electric Company to M. Fairtile..U.S. Nuclear Regulatory Commission, dated May 22, 1992 (d)
Letter, D. Crutchfield, U.S. Nu, ear-Regulatory Commission to J.-Kay, Yankee Atomic Electric Company..
dated March 30,:1984, 1
Subject:
PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS
Dear'Mr. Fairtile:
Pursuant to 10 CFR 50.90 of the Commission'sLRules and Regulations, l,
Yankee Atomic Electric Company (YAEC) hereby-requests-the. authorization-to
'make the following changes to the-facility license;and to' Appendix A'of the facility license. 'The request is in-recognition of the fact that the Yankee Nuclear Power Station (YNPS) is' permanently shutdown and defueled and holds a Possession Only License (Reference (b)).
PROPOSED CHANGE Reference is made to the YNPS Technical Specifications and Possession L
_0nly License No, DPR 3.
We propose to modify the License and-Technical-ic Specifications 'to reflect the. permanently shutdown and defueled. status. The-specific' changes and their reasons and bases, are presented in Attachment A.
Attachment B provides~a revised page 4 to the Possession Only' License.
~1-Attachment C presents-a full replacement document for the YNPS Technical R72\\B0 -
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'v-United States Nuclear Regulatory Commission December 21, 1992 Document Control _ Desk Page 2-1 BYR.92 112 ll Specifications.
Both attachments integrate the specific changes _ described in:
Attacoment A.
l REASON AND BASIS FOR CHANGE YNPS parmanently ceased: power operations as of February 26, 1992.
All:
spent fuel-is being stored in the Spent fuel Pit.- The-Possession Only License _
prohibits the movement of fuel from the Spent fuel Pit into the Vapor Container (containment building).
The changes proposed herein reflect-the limitations and requirements appropriate to the Possession Only: License and Permanently Defueled Technical Specifications.
The primary reason for this change is to simplify and to -
improve clarity by. eliminating the large volume of non-applicable; material in the current License and Technical Specifications. The objective.is a clear and concise document for maintaining the facility in a permanently defueled condition.
Specific reasons _and bases for each change are included 1in the detailed listing of Attachment A.
SAFETY CONSIDERATIONS
-YNPS holds a Possession Only License which permanently restricts the facility from power operations and from moving nuclear fuel into the containment building.
Maintenance of the facility has been significantly simplified with the reduction in the_ numbers of_ systems, structures and. components-required;for the permanently shutdown and-defueled condition. -The accident-analyses have~
been revised, incorporating the new restrictions and configurations, and conclude the only credible accident remaining is the fuel-handling accident.
The changes-described herein incorporate the changes and analytical results_into the Possession Only-License and its Technical Specifications, simplifying and-clarifying-both.
As such, these changes will1not:
1 Involve a significant increase _ in the probability or consequence 'of 'an I
accident'previously evaluated. The revised-analyses -indicate thationly-the fuelfhandling~ accident remains credible. The proposed _ changes 2
incorporate into the Technica1' Specifications requirements-from these analyses and thus do not involve a significant increase in the probability or consequence of an accident previously evaluated, y
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' United = States Nuclear Regulatory Commission
' December 21, 1992-Document Control Desk -
Page 3
'BYR 92-112 2
Create the possibility of a-new or different kind of accident from any-accident previously evaluated. -The proposed-changes integrate into the 1Technica1' Specifications previously= evaluated accidents and thus do not create the possibility of a new or different kind of accident from any previously evaluated.
3 Involve a significant reduction in a margin of safety.
The proposed changes incorporate into the Defueled Technical Specifications the margin of safety associated with the current safety analyses and thus do not involve a significant reduction in a margin of safety.
Based on the above considerations, it is concluded that there is reasonable assurance that the maintenance of Yankee Nuclear Power Station consistent with the proposed changes, will not endanger the health and safety of the public.
This proposed change has been reviewed by the Plant Operations Review
' Committee and the Nuclear Safety Audit and Review Committee.
SCHEDUlf 0F CHANGE These page changes to the YNPS Technical Specifications will be made upon the Commission's approval.
We trust you will find this submittal satisfactory; however, should you desire aoditional information, please contact Jane Grant or me.
Very Truly Yours, YANKEE ATOMIC ELECTRIC COMPANY I
so-
.i J. K. Thayer Vice President and Manager of Operations tkh c:
USNRC Region 1 USNRC Resident Inspector, YNPS R. Dudley, NRC, NRR Attachments R72iA0
>a-United States Nuclear RegulatoryECommission-December 21, 1992 Document Control Desk Page 4 BYR 92-112 COMMONWEALTH OF MASSACHUSETTS)
)ss WORCESTER COUNTY
)
Then personally appeared before me, J. K. Thayer, who, being duly sworn, did state that he is a Vice President and Manager of Operations of Yankee-Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Yankee Atomic Electric-Company and.that-the statements therein are true to the best of his knowledge and belief.
AbuL{lara,,nar Helen D. 3~ mmarco Notary Public a
My Commission Expires October 16, 1998 A7h 80
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ATTACHMENT A
SUMMARY
OF CHANGES TO 3
LICENSE 0, OPR-3 AND TECHNICAL SPECIFICATIONS-4 y
j The following changes, reasons and bases ar e organized numerically in accordance with the current Licanse and Technical Specifications, t-3-
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- Attachment A-POSSESSION'ONLY LICENSE'(pace 3) e Chances--
1.
Revise paragraph 2.C.(3).
Reasons and Bases 1.
' Paragraph 2.C.(3) i s revised to reflect YNPS' implementation of -a Defueled Security Plan and a. Defueled Security Training and Oualification Plan. -Both plans were approved by NRC vi_a an-
. exemption request. The-exemption was granted on' November 24, 1992.
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Attachment ~A-i POSSESSION'ONLY ' LICENSE (pace 4) y Changes-l 1.
~ Delete paragraph 2.C.(6).
2.
Delete paragraph 2.C.(7).
3.
Delete paragraph 2.C.(8).
.4, Renumber license conditions sequentially: consolidate pages..
Reasons'and Bases
- 1.
Paragraph 2.0.(6) placed a temporary limitation of 391 on the number. of spent fuel assemblies stored in the Spent Fuel Pit,=
pending the resolution of seismic analyses.
Resolution of the seismic issues was -documented in reference (d)
(NYR 84-60).and the conditions of the restriction were satisfied as of March 30, 1984.
Current Technical Specification 5.6.3 limits the number of. fuel' assemblies to 721.
The limit will be retained in the Defueled Technical Specifications. 'The actual number of fuel assemblies now in the Spent Fuel Pit is 533.
As of the date of resolution (March 30, 1984), this paragr6ph ceased to have any bearing on the license.
Accordingly, it1should.
be deleted.
2.
Paragraph.2.C.(7) was imposed in response to NVREG 0578, TMI Lessons Learned (7/18/79), which required a leakage _ monitoring program-to reduce leakage from systems outside containment'that-could contain highly radioactive fluids during a serious transient.
or accident.
The origin of this requirement was the 1979_ accident at THI, during_which the RHR system was unavailable for use in_its intended configuration because the. potential for excess leakage outside containment was too great.. A general requirement.was then
-formulated to include minimizing-the leakage-from any system outside containment which could be used during an accident to transport highly radioactive'fiuids, liquid or gaseous.
The location-of an accident capable of' producing highly radioactive fluids (doses greater than Part 100' limits) was.
assumed to be an operating reactor; vessel.
It was-not (and ist not) the spent fuel pit.
Because the plant is permanently
' shutdown and defueled. the only remaining credible-design' basis
-event at YNPS is.a fuel handling accident.
However, a fuel 1.
nsu 2
Attachment _A handling accident in the spent fuel pit will not result in the release of liquid or gaseous ef fluents which could exceed Part 100 limits.
The reactor is defueled and the plant is prohibited f rom power operations by the Possession Only License.
Because none of the systems previously governed by this requirement remain a potential source of highly radioactive fluids, and because there is no source of highly radioactive fluids f rom the spent fuel pit, the purpose of the requirement ceases to apply to YNPS.
Protection of the public from a Part 100 release has been permanently achieved via the shutdown and defueling of YNPS.
3.
Paragraph 2.C.(8) requires a program to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
The only remaining credible accident at YNPS is a fuel handling accident.
However, a fuel handling accident will not produce ef fluents which could exceed Part 100 limits.
For example, conservative analyses of thyroid doses from 1-129 in the event cf a fuel handling accident yield results in orders of magnitude below Protective Action Guidelines (PAG) and 10 CFR 100 limits.
YNPS was shutdown on October 1, 1991, and declared permanently shutdown as of February 26, 1992.
Over fourteen months have elapsed since the shutdown.
Dose significant radionuclides of iodine other than 1-129 have undergone at least 53 half lives since shutdown, at least a sixteen order of magnitude reduction.
Therefore, radiological dose consequences from radioactive iodine are negligible at this time.
With negligible dose consequences from radioactive iodine in the spent fuel, and no other source of radioactive iodine, there is no purpose for the requirement to maintain a program to accurately measure thc concentrations in vital areas.
It should be deleted.
4.
License Conditions on Page 4 of the POL were renumbered to reflect the fact that several license conditions are deleted.
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' 'E Attachment A
.-APPEND]X 'A'-TO LICENSE N0; DPR - 3 1
' TECHNICAL SPECIF; CATIONS INDEX Changes 1.
-Renumber and revise according to the changes described herein'.
Reason and Basis 1.
Renumbering and revising the Index,-in accordance with the changes.
listed below, will improve the clarity and consistency of this major revision to the Technical Specifications.
1.0 DEFINITIONS Chancet 1.
The following definitions have been retained, reordered-alphabetically, and renumbered:
1.1 ACTION 1.2 CHANNEL CALIBRATION 1.3 CHANNEL CHECK 1.4-CHANNEL FUNCTIONAL TEST 1.5 MEMBER (S) 0F THE-PUBLIC-1.6 0FF-SITE DOSE CALCULATION MANUAL-(ODCM) 1.7 OPERABLE-0PERABILITY.
1.8 PROCESS CONTROL ~ PROGRAM (PCP)-
1.9 REPORTABLE EVENT 1.10 SITE BOUNDARY 2.
Definitions-for the following have been deleted:
. THERMAL POWER-RATED THERMAL POWER 0PERATIONAL-MODE (including. TABLE.1.1)
CONTAINMENT-INTEGRITY CORE ALTERATION SHUTDOWN MARGIN-IDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE PRESSURE' BOUNDARY LEAKAGE DOSE' EQUIVALENT I-131
. STAGGERED TEST BASIS-FREQUENCY NOTATION. (including TABLE 1.2) y.
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Attachment A 1
PHYSICS TESTS E AVERAGE DISINTEGRATION ENERGY SOURCE CHECK i
GASLOUS RADWASTE TREATHENT SYSTEM VENTILATION EXHAUST TREATMENT iURGE PURGING l
Sbt!DIFICATION l
CORE OPERATING LIMITS REPORT REDUCED LEVEL OPERATION l
3.
The word ' safety
- was inserted into.the definition of-OPERABILITY.
4.
Reference to production of electricity was removed from the definition of MEMBER (S) 0F THE PUBLIC.
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I Reasons and Bases 1.
The definitions retained continue to be refereh;ed by the i
remaining Technical-Specifications.
j 2.
The definitions deleted are no longer referred to within the l
remaining Technical Specifications.
3.
Inserting the word " safety' into the definition of OPERABILITY differentiates between the safety function of a system, subsystem, I
train, component or device and its other functions which may exist aurely for ease of-maintenance.
There is no reduction in the
- ope of the definition for applicable Technical Specification anctions.
4 Reference tt a,Juction of electricity is no long1r appropriate given the permanently shutdown and defueled status of YNPS.
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Attachment A 2.0 SAFETY LIMITS i
Chance 1.
Delete all of the subsections of 2.0 SAFETY llHITS:
j 2.1 SAFETY LlHITS f
2.2 LIMITING SAFETY SYSTEM SET 11NGS Reasons and Bases i
1.
These subsections address issues of Thermal Power, Main Coolant l
System Pressure and Reactor Protective System Instrument Setpoints i
associatcd with power operations.
These subsections are not required to support the Possession Only License.
Specifically:
j i
2.1.1 Reactor Core i
s This_ safety limit prevents overheating of the fuel that would result in releasing fission products to the main coolant system (MCS).
Because the reactor vessel-is permanently.defueled limits'affecting full integrity in the.
reactor vessel are not needed.
2.1.2 Main Coolant System Pressure This limit prevents release of radionuclide: into-the vapor container by protecting MCS integrity from t
overpressurization events.
The reactor vessel is permanently defueled and the HCS radionuclide inventory is very low.
Release of significant quantities of radionuclides following an overpressurization event is not poss'ble.
I 2,P.1 Rea; tor Protective System Instrumentation Setpoints This section prese,t reactor trip setpoints for each channel required rv 1 schnical Specification 3.3.1.
Because the reactor vessel is permanently defueled, reactor trips are no longer needed to ensure safety limits are not exceeded.
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Attachmen(_A
-3/4,0 APPLICABILITY Changes 1.
The following subsections were retained with the noted changest 3.0.1 Substitute the words 'specified applicable condition
- for ' OPERATIONAL MODES or other conditions specified'.
3.0.2 No change.
3.0.4 Renumbered as 3.0.3 with the last sentence deleted.
4.0.1 Substitute ths words 'specified applicable condition
- for *0PERATIONAL MODES or other conditions-specified*.
4.0.2 No changc.
4.0.3 No change.
4.0.4 Substitute the words 'specified applicable condition' for ' OPERATIONAL MODES or other conditions specified*.
2.
The following subsections were deleted.
3.0.3 3.0.4 (last sente.ce only) r 3.0.5 4.0.5 Reasons and Bases 1.
Deleting references __to OPERATING MODES is consistent with the Possession Only License which prohibits power operations.
Substituting the words 'specified applicable condition" for
- OPERATIONAL MODES or other conditions specified" retains the intent of the applicability for the conditions specified.in each' Limiting Condition for Operation.
2.
The deleted specifications _are all requirements specific only to operating modes.
The_ Possession Only License. prohibits operations in any operating mode.
Therefore these specifications are not applicable.-
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' Attachment A 3/4.1 REACTIVITY CONTROL SYSTfMS Chance j
l 1.
Delete ch
- subsections of 3/4.1 REACTIVITY CONTROL SYSTEMS l
(Pages i i through 3/4 1 29):
3/4.1.1 B0 RATION CONTROL 3/4.1.2 BORATION $YSTEMS 3/4.1.3 MOVEABLE CONTROL RODS
-Reason and Basis F
1.
These specifications limit the reactivity condition (e.g. shutdown margin, control rod operability, moderator temperature-coefficient) of the reactor core.
The reactor vessel is-permanently defueled.
Therefore, reactivity controls for the reactor core are not needed.
3/4.2 POWER DISTRIBUTION LIMITS Chance 1.
Delete all of the subsections of 3/4.2, POWER DISTRIBUTION LIMITS-(Pages 3/4 2-1 through 3/4 213):
3/4,2.1 PEAK LINEAR HEAT GENERATION RATE 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4.2.4 DNB PARAMETERS Reason and Basis 1.
These specifications limit power distribution in the reactor to ensure fuel integrity is maintained during operation. The reactor vessel is permanently defueled.
Therefore, fuel integrity controls pertaining to the reactor-core are not needed.
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Attachment A 3/4-3 INSTRUMENTATION Chanog 1.
Delete the following subsections of 3/4.3 INSTRUMENTATION:
3/4.3.1 REACTOR PROTECTIVE SYSTEM INSTRUMENTATION 3/4.3.2 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION 3/4.3.3.1 RADIATION HONITORING INSTRUMENTATION j
(except for the Spent fuel Pit area radiation monitors described in item 2 below) l 3/4.3.3.2 INCORE DETECTION SYSTEM 3/4.3.3.3 NETEOROLOGICAE INSTRUMENTATION 3/4.3.3.S ACCIDENT HONITORING INSTRUMENTATION 3/4.3.3.7 EXPLOS!VE GAS HONITORING INSTRUMENTATION 2.
From subsection 3/4.3.3.1 RADIATION HONITORING INSTRUMENTATION.
retain specifications for the Spent Fuel Pit area radiation monitors as new section 3/4.3 of the Technical Specifications.
Also, change the-format of new specification 3/4.3 for the Spent l
Fuel Pit area radiation monitor to remove the use of a TABLE.
Revise the wording of the ACTION' Statement.
3.
Retain subsection 3/4.3.3.3 METEOROLOGICAL INSTRUMENTATION as new specification 3/4.6. with two changes a.
References to other Technical Specifications and Tables were updated to be consistent with the changes described herein, b.
References to instrumentation at nominal elevation 33 feet have been deleted.
Reasons and Bases 4
1.
These subsections are associated with fuel in the reactor vessel and/or power operation of the facility.
They are not required because the Possession Only-License prohibits' power operations and further prohibits movement of fuel into the reactor vessel.
Specifically:
3/4.3,1-Reactor Protective System Instrumentation 1This specification ensures the operability of the: Reactor Protective System. The reactor vessel is permanently.
defueled and reactor trips.are.not needed, ainaa 9
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Attachment A
'3/4.3.0
. Engineered Safeguards System Instrumentation-This specification ensures the operability of the Engineered Safeguards System (ESS) instrumentation: Safety injection Actuation. Main Steam Isolation Actuation, and Emergency Bus-Loss of Power Actuation.
With the reactor permanently defueled. the design basis accidents mitigated by the ESS are no longer possible.
ESS instrumentation are not needed.
3/4.3.3.1 Radiation Monitoring Instrumentation Except for the Spent Fuel Pit area radiation monitor the -
1 instrumentation specified in this subsection addresses circumstances related to power operation. The instrumentation includes containment area.-$ team generator blowdown, steam line, containment refueling monitor, and vent stack noble gas monitors. Appropriate area radiation monitors will be included under administrative controls.
The Possession Only license prohibits both power: operation-and transfer of fuel into containment.
Therefore, the only monitor which remains applicable is the Spent Fuel Pit area radiation monitor.
See item 2 below.-
3/4.3.3.2 Incore Detection System This specification ensures that the incore detection-system measures the core power distribution.
Power distribution-3 measurements are needed to comply with the-surveillance recJirements.in Technical Specification 3/4.2.
However.
3/4.2 is-not applicable when the-reactor vessel cis defueled.
Therefore, the incore detection system is no longer.needed.
3/4.3.3.3 Meteorological Instrumentation This specification ensures the capability to evaluate the need for initiating protective measures to protect the health and rafety of the public.. The Defueled Emergency Plan. which reflects the_ permanently shutdown and defueled status of YHPS. does not require-protective action recommendations-be made-to-the public.because.there-are no l
postulated accidents which could. result:in the ' release of radioactive materials to.the environment:in quantities lwhich-would require protective-actions for the:public.
Analyses demonstrate' that at the exclusion area ' boundary, the:whole -
body-dose, the thyroid ~ dose, and the skin -dose would be small f ractions of the EPA's. Protective Action-Guidelines.-
As a consequence..the need for the towercis reduced to the anwo.
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Attachment A support of routine effluent controls identified in the ODCM and determination of wind speed and direction as required by the Defueled Emergency Plan.
Transfer of the requirement for the meteorological tower is made on the same basis as the justification used to transfer routine effluent monitoring and dose calculated requirements into the OOCH (Generic Letter 89 01).
3/4.3.3.5 Accid (nt Monitoring Instrumentation This specification ensures operability of instrumentation used to monitor plant conditions during and following an accident affecting the MCS or containment. With the reactor vessel permanently defueled, however, accidents requiring these monitors are no longer possible.
Therefore, the accident monitoring instrumentation are no longer needed.
3/4.3.3.7 Explosive Gas Monitoring Instrumentation This specification ensures _that the limits-of-Specification-3.11.2.5 are not exceeded.
Specification 3.11.2.5 will be deleted as part of a Technical Specification request (PC 256) filed with the NRC on September 16. 1992.
Since-the permanent cessation of power operations, the Waste Gas Holdup System has been purged and vented with air.
Hydrogen is no longer added to the Main Coolant System. thereby.
eliminating the need for-explosive gas monitoring.
2.
Applicability for Spent fuel Pit area radiation monitors continues with the Possession Only License.
The table format 'is not warranted because only one type of_ instrumentation is retained.
The ACTION Statement was revised to more accurately reflect the intent of the specification and to be consistent with new Specification 3/4.1.
3.
Updating the cross references to other Technical Specifications was made necessary by changes in nearly all numbering within the proposed Technical Specifications.
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Attechment A j
3/4.4 MAIN C00LA41_ SYSTEMS 3
i Chanae 1.
Delete all of the subsections of 3/4.4. MAIN COOLANT SYSTEMS (Pages 3/4 4 1 through 3/4 4 39):
3/4.4.1 MAIN COOLANT LOOPS 3/4.4.2 SAFETY VALVES-SHUTDOWN 3/4.4.3 SATETY VALVES-0PERATlHG 3/4.4.4 PRESSURIZER 3/4.4.5 MAIN COOLANT SYSTEM LEAKAGE 3/4.4.7 SPECIFIC ACTIVITY 3/4.4.8 PRESSURE /TEMPLAATURE LIMITS 3/4.4.9 STRUCTURAL INTEGRlTY 3/4.4.10 STEAM GENERATORS
'l 3/4.4.11 MAIN COOLANT SYSTEM VENTS Reasons and Bases 1.
These subsections address issues that are associated with fuel in the reactor vessel and/or power operation of the facility. These subsections are not required because the Possession Only License prohibits power operations and further prohibits movement of fuel into the reactor vessel and vapor container.
Specifically:
3/4.4.1 MAIN COOLANT LOOPS This specification ensures the following:
Departure from nucleate boiling ratio (13 J
Residual heat removal capability.
Reactivity transielts do not occur during_
isolated loop start-up MCS overpressurization does not occur during main coolant pump starting With the recctor permanently defueled, control of DNBR.
residual heat amoval capability..and reactivity in the MCS is not needed.
R91 ease of significant quantities of radionuclides fol)owing a MCS overpressurization event.is-not possible regarCless of the source of the overpressurization.
Therefore.- main-coolant pump starting limitations are no longer.needed. Specification 3/4.4.'_1 is, not needed, unei 12
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Attachment'A 3/4.4.2 SAFETY VALVES - SHUTOOWN This specification ensures the MCS pressure is maintained; below the limits presented in Technical Specification 2.1.2.
With the reactor vessel permanently defueled, the MCS radionuclide inventory is very low Release of significant 1
quantities of radionuclides following.an overpressurization
)
event is not possible.
3/4.4.3 SAFETY VALVES OPERATING i
This specification ensures _that the HCS pressure is_
maintained below the limits presented in Technical:
Specification 2.1.2.
With the reactor vessel permanently defueled'. the=radionuclide inventory is very low.
Release of significant quantities-of radionuclides following an overpressuritation event is not possible.
_l 3/4.4.4 PRESSURIZER This specification ensures the following:-
MCS can accommodate pressure surges Pressurizer heaters can be energized to support natural circulation cooling Pressurizer safety-valves are protected against.
water relief Pressurizer operational capabilities are needed to accommodate transients that occur-during power operation.
However, the reactor is permanently defueled and prohibited from power operation.
These capabilities are not needed.
i 3/4.4.5 MAIN COOLANT SYSTEM LEAKAGE.
This. specification ensures earlyf detection _of leakage so that appropriate actions can be taken_before pressure-boundary failure occurs.
With the reactor permanently:
defueled, the MCS'radionuclide inventory is very low.
Release'of significant quantities of radionuclides following, pressure boundary failure will not occur.- Therefore, the leakage limits are'not needed.
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Attachment A 3/4.4.7 SPECIFIC ACTIVITY This specification ensures that radiological releases resulting from a design basis steam generator. tube rupture are significantly less than 10 CFR 100 limits.
With the reactor permanently defueled, the rupture of steam generator tubes is no longer a credible design basis event.
Therefore, this specification is no longer needed.
l 3/4.4.8 PRESSURE / TEMPERATURE LIMITS i
This specification ensures the integrity of all components of the Main Coolant System by conservatively controlling the 4
effects of cyclic loading during normal load transients, reactor trips, startup and shutdown operations.
However,-
I the reactor-is permanently defueled and power operation is prohibited by the Possession Only License.
The conservative protection provided by this specification is no longer
- needed, j
3/4.4.9 STRUCTURAL INTEGRITY This specification addresses the ASME Section?XI inspection, examination and testing requirements for Code Class systems-1, 2 and 3 components.
The inspections verify the integrity of high pressure and temperature systems.
The. remaining-functional systems at YHPS are relatively low pressure-and temperature systems. Therefore, high temperature / pressure erosion and corrosion is not. expected, ASME-Section XI.-
q Section IWA-2400(c) provides for deferral of inspections due to extended plant outages.
Furthermore,10 CFR 50.55a(g),
s which requires an examination and testing program in
[
occordance with ASME Section XI,-is predicated on power operations, The POL prohibits power' operations.
Therefore, these inspection and examination requirements are noLlonger needed.
3/4.4.10 STEAM GENERATORS This specification ensures the operability of the steam generators based on inservice inspection of the tubes.-
Structural integrity is needed to minimize the probability' of a' steam generator tube rupture.
However, with the-reactor permanently defueleo, a steam' generator tube rupture with a significant radiological release consequence is not possible.
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3/4.4.11 MAIN COOLANT SYSTEM VENTS-This specification ensures the operability of the main coolant system vent system.
The system vents gases from the p
HCS that could inhibit natural circulation following reactor shutdown.
The reactor is permanently defueled. therefore HCS natural circulation capability is not needed.
i 3/4,5 EHERGENCY CORE COOLING SYSTEM Chance i
1.
Delete all subsections of 3/4.5 EMERGENCY CORE COOLING SYSTEM:
(Pages 3/4 5 1 through 3/4 5 13) i 3/4.5.1 ACCUMULATORS 1
3/4.5.2 ECCS SUBSYSTEMS /HIGH PRESSURE-3/4.5.3 ECCS SUBSYSTEMS /lHTERHEDIATE PRESSURE 3/4.5.4 ECC5 SUBSYSTEMS / LOWER TEMPERATURE
~
3/4.5.5 SAFETY ins 1ECT10N TANK 3/4.5.6 ECCS SUBSYSTEH LEAKAGE i
Reason and Basis 1.
These specifications ensure the operability of the emergency core cooling systems and prevent inadvertent Hain' Coolant System i
overpressurization. With the reactor permanently defueled, the1 design basis events-that are mitigated by the emergency core cooling systems are not possible.
i These specifications address issues associated with fuel in.the reactor vessel and/or power operation of the facility.
They are
-not required because the Possession Only License prohibits power-operations'and further' prohibits movement of fuel into the reactor vessel and vapor container.
3/4.6 CONTAINHENT SYSTEMS Change 1.
Delete all subsections:of 3/4.6-CONTAINHENT SYSTEMS::
(Pages 3/4 6 1 through 3/4 6 18) t 3/4.6.1 PRIMARY CONTAINHENT-3/4.6.2 CONTAINMENT ISOLATION VALVES 3/4.6.3 COMBUST!BLE GAS CONTROL unna IS' I.,----,
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Attachment A Reason and Basis 1.
These subsections address issues associated with fuel in the reactor vessel.
Specifically, these subsections ensure that leakage.from the vapor container following a design basis event remains within the limits assumed in the analysis. However, the reactor is permanently defueled.
Furthermore, the POL prohibits the transfer of f uel from the Spent Fuel Pit _into the vapor container.
Therefore. there are no design basis events that result in the significant release of radionuclides inside the vapor container.
Containment integrity in the context of Specification 3/4.6 is not needed.
2/4,7 PLANT SYSTEMS i
Chance 1.
Delete the following subsections of 3/4-7 PLANT SYSTEMS:
3/4.7.1-TURBINE CYCLE--
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITA110N 3/4.7.5 CONTROL ROOM EHERGENCY AIR CLEANING 3/4.7.9 SNUBBERS 2.
Retain subsection 3/4.7.6 SEALED SOURCE CONTAMINATION as new Technical Specification 3/4.5 with the following changes:
a.
Renumber the specifications, including the reference to other Technical Specifications.
I b.
Delete ACTION b and SURVEILLANCE REQUIREMENT 4.7.6.2.c.
Reasons and Bases l
1.
These subsections address issues associated with;the power operation of the facility.
These subsections are not required because the Possession Only License prohibits power operations. -
Specifically:
- 3/4.7.1 TURBINE CYCLE This specification ensures the following:
Steam system pressure will not exceed the system design pressure Feedwater capabilities are maintained following'a. loss l.
of power event o
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Attachment A Assumptions in the steam line rupture design basis accident analysis are not exceeded The reactor-is permanently defueled and design basis accidents effecting the steam system are not possible.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION This specification ensures that pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress _ limits.
Ensuring steam generator integrity is no longer needed.
The reactor'is permanently defueled design basis accidents affecting the steam generators are not possible.
3/4.7.S CONTROL ROOM EMERGENCY AIR CLEANING SYSTEH This specification ensures control room habitability following a design basis accident.
The reactor is 2
permanently.defueled.
The POL prohibits'the-transfer of-fuel from the Spent Fuel Pit into the vapor container.
The l
only remaining design basis event for this configuration is a Fuel Handling Accident.
The Fuel Handling Accident I
analysis does not take credit for availability of the i
Control Room Emergency Air Cleaning System to_ limit dose to site personnel.
Therefore, this specification is no longer needed.
3/4.7.9 SNUBBERS This specification ensures the structural integrity of the MCS and all other safety related systems is maintained following a seismic or other event -initiating dynamic loads.
_ 4 Hone of the safety related snubbers presented in Table 3.7 4-are associated with systems that are required to be operable during permanently defueled operations.
This specification is no longer applicable.
-2.a The specification for SEALED SOURCE CONTAMINATION is necessary at all times, regardless of operating status.. Renumbering the specification'is necessary due to the significant restructuring-associated-with the other changes described herein.
2.b
. SURVEILLANCE REQUIREMENT 4.7.6.2.c addr' esses startup source i
surveill_ance prior to power operations and should be deleted._
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' i Attachment A 3/4.8 ELECTRICAL POWER SYSTEMS-
]
Change f
1.
Delete all subsections of 3/4.0 ELECTRICAL POWER SYSTEMS:
(Pages 3/4 8-1 through 3/4 8 11) 3/4.8.1 AC SOURCES i
3/4.8.2 ON SITE POWER DISTRIBUTION SYSTEMS Reason and Basis 1.
These specific 0tions ensure that electrical system operability limits are maintained during Modes 1 through 6.
There are no electrical system specifications applicable during defueled operations.
In the event that spent fuel pit cooling capability c6nnot be established, make up weter flow at about 2 gpm must be established to replace water inventory lost through evaporation._ Diverse.
l means are available that do not rely on the normal power distribution system (e.g., gravity feed from the fire tank, l
pumping from the reservoir with a fire truck or a gas driven pump, pumping with the fire and service water systems).
Furthermore, the need to provide immediate back-up electrical power is diminished due to the significant amount of time available to restore cooling of the spent f uel pit (>3-weeks).. In addition.
YNPS has two separate preferred off-site sources of electrical power. An evaluation of the off-site e10ctrical grid for YNPS was performed to satisfy 10 CFR 50.63. Station Blackout, and verified the stability of the grid. _ Off-site power reliability, diverse i
means of providing spent fuel pit inventory make up, and.
- significant amount of-time to-take corrective actions-eliminate-the need to rely on the emergency diesel generators as the sole back up capability supporting spent fuel pit operations.
An emergency diesel generator is maintained available as NNSL equipment under acininistrative controls.
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Attachment A 3/4.9 REFUELING OPERATIONS Chance 1.
Delete the following subsections of 3/4.9 REFUEllHG OPERATIONS:
i 3/4.9.1 REACTIVITY 3/4.9.2 INSTRUMENTATION 3/4.9.3 DECAY TIME 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4.9.6 SHIELD TANK CAVITY MANIPULATOR CRANE OPERABILITY 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.9 CONTAINMENT PURGE FAN SHUTDOWN SYSTEM 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4.9.12 SPENT FUEL PIT BUILDING ISOLATION 2.
Retoin subsection 3/4.9.7 CRANE TRAVEL SPENT FUEL PIT as.new Technical Specification'3/4.2. deleting SURVEILLANCE REQUIREMENT 4.9.7.2.
In new LCO 3.2 and SURVEILLANCE REQUIREMENT 4.2.1, revise " Spent Fuel Pit Building" to " Spent fuel Storage Building
- to be consist 9t with current terminology.
3.
Retain subsection 3/4.9.11 SPENT FUEL PIT WATER LEVEL as new Technical Specification 3/4.1.
Revise the wording of the Action.
statement.
I Reasons and Bases 1.
These subsections address issues associated with fuel in the reactor vessel.
These subsections are not required because the-Possession Only License prohibits power operations and further prohibits movement of fuel into the reactor vessel and vapor
,-i container.
Specifically:-
3/4.9.1 REACTIVITY This specification ensures that the reactor remains subcritical' during core alterations and that boron concentration is uniform. -The reactor is permanently
.defueled and core alterations will not occur.
3/4 9.2 INSTRUMENTATION This specification maintains redundant monitoring capability-of reactor core reactivity conditions during core min 19
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Attachment A i
alterations.
The reactor is permanently defueled and core
-alterations will not occur.
i 3/4.9.3 DECAY TIME This specification ensures that sufficient time has elapsed j
before fuel movement to allow for radioactive decay of short l
lived fission products.
The reactor is permanently defueled and has been shut down for greater than the minimum 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.
This limit is not needed.
3/4.9.4 CONTAINHENT BUILDING PENETRATIONS l'
This specification ensures that any radionuclide releases to the environment resulting from fuel damage occurring _during core alterations or movement of--irradiated fuel will be limited.
The reactor is-' permanently defueled.
Core
-j alterations and fuel movements within containment will not' occur.
3/4.9.5 COMMUNICATIONS This specification ensures that refueling personnel are promptly informed of changes to facilit/ status or y
reactivity conditions during core alterations.
The reactor l
is permanently defueled.
Therefore, core alterations will not occur.
3/4.9.6 SHIELD TANK. CAVITY MANIPULATOR CRANE OPERABILITY' This specification ensures-the following:
The manipulator crane and universal handling tool are used for the movement of fuel. and -
~;
control rods Manipulator crane and universal handling tool have sufficient load _ capacity Core internals andfreactor pressure-vessel are protected against excessive. lifting forces-J The reactor is_ permanently defueled, and the control = rods have been removed.. Movement of fuel and control: rods in-containment will-not occur.
Protection of'the core-internals and reactor pressure vessel.is not needed because.
. fuel will not be reloaded into the reactor, q
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Attachment'A 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION
-This specification ensures-the following Sufficient cooling capacity is available to maintain the MCS below 140*F during refueling Sufficient cooling circulation is maintained to prevent boron concentration gradients Redundant residual heat removal loops are available when water level is less than 32 feet above the fuel The reactor is permanently defueled.
Residual heat removal:
in the reactor vessel and boron mixing is not needed.
3/4.9.9 CONTAINMENT PURGE FAN SHUTDOWN SYSTEM t
This specification ensures that the containment purge fan can be shut down upon the detection of high radiation levels in the vapor container during core alterations.
The reactor is permanently defueled.
Therefore, core alterations will not occur.
3/4.9.12 SPENT FUEL P!T BUILDING ISOLATION The dose evaluation for the Fuel Handling Accident analysis does -not credit the availability of. the Spent fuel Building.
Isolation System to limit dose-to the public or' site personnel.
Therefore, this specification-is not needed.
2.
Retaining subsection 3/4.9.7 CRANE TRAVEL SPENT FUEL PIT as.new-3/4.2 requires renumbering to support the significant changes described herein.
The deletion of SURVEILLANCE REQUIREMENT-4.9.7.2 is appropriate because it is only' applicable when there are newly (60 days or less) discharged fuel assemblies in the.
i Spent fuel Pit.
The most recently discharged fuel assemblies in
?
the YNPS Spent Fuel Pit _last operated over a year ago and were discharged more than 9 months:ago.
By license, no newly.
discharged fuel assemblies may be.added and-there is no newly =
discharged-fue1~. 'The.nord'* roof' is added to SVRVEILLANCE REQUIREMENT 4.9.7.1 (new 4.2.1) to clarify ' hatches '
.3.
Retaining subsection 3/4.9.11 SPENT. FUEL PIT WATER LEVEL.as new 3/4.1 requires-renumbering to support-the significant changes described herein, A reference to power operation was also deleted from the ACT!0N statement, and the wording was revised to more accurately reflect the intent of the specification.
i neau 21 i
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.--.__-_._____._____.-._._______._m
)
Attachment A jf \\_.10 SPECIAL TEST EXCEPTIONS 1
Changg 1.
Delete'all subsections of 3/4.10 SPECIAL TEST EXCEPTIONS:
(Pages 3/4 10 1 through 3/4 10 9) i 1
3/4.10.1 SHUTDOWN MARGIN 3/4.10.2 CONTROL R0D OPERABILITY AND INSERTION LIMITS 3/4.10.3 PRESSURE / TEMPERATURE LlHITATION i
3/4.10.4 PHYSICS TESTS 3/4.10.0 REDUCED LEVEL OPERATION WITHOUT COLD LEG OPENING 3/4.10.6 REDUCED LEVEL OPEAATION WITH COLD LEG OPENING 3/4.10.7 REDUCED LEVEL OPERATION FOR COLD LEG OPENING WITH LOW DECAY HEAT Reason and Basis 1.
These specifications impose limits restricting plant operation during physics-testing and reduced inventory operations.
The__
reactor is permanently defueled and physics testing and reduced level operations will not occur.
These subsections are not l
required because the Possession Only License prohibits power operations and prohibits movement of fuel into the reactor vessel and vapor container.
jfQ1 RADI0 ACTIVE EFFLUENTS Change 1.
Delete the following subsections of 3/4.11 RADIDACTIVE EFFLUENTS:
1 3/4.11.2,6 GAS STORAGE TANK 2.
Retain subsection 3/4.11.1.4 L10VID HOLDUP TANKS as new Technical Specification 3/4.4. renumbering and' deleting ACTION b.
Revise the wording of the specification.
Reasons and Bases 1.
Subsection 3/4.11.2.6 addresses issues associated with fuel in the reactor vessel.
The Possession Only License for'YNPS_ prohibits power operations and prohibits movement of fuel into the-reactor-vessel.
Furthermore. the Waste Gas-System, including the waste gas storage tank. has been purged and is not'used to store gaseous-fission products in the plant's defueled configuration.
The i
potential release of gaseous; inventory from the -spent fuel pit Lis considered to be bounding for any_possible-radioactive gas release uneo.
22 6
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Attachment A while the plant is defueled.
(All other pages in subsections 11 and 12 are blank).
2.
Retaining subsection' 3/4.11.1.4 t.10010 HOLOUP TAHKS as new 3/4.4 requires renumbering to support the significant changes descrited herein.
A reference to power operation was also deleted from the ACTION statement.
The ACTION statement was also revised for clarification.
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Attachment A l
BASES FOR SECTIONS 3,0 AND 4.0 t
i Chance 1.
BASES for-specifications removed from the Technical Specifications were also removed.
l 2.
BASES for specifications remaining in the Technical Specifications were revised to reflect the current limited use of the facility.
l t
Reasons and Bases 1.
The BASES for Technical Specifications removed are no longer needed in the Technical Specifications.
2.
The BASES for Technical Specifications remaining were revised for-consistency to explain the reasons for the Specifications in Section 3/4.
However, in accordance with 10 CFR 50.36, they are not part of these Technical Specifications.
L I
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Attachment A 5.0 DESIGN FEATURES Chance 1.
The following subsections were retained:
5.1.1 SITE 5.6 FUEL STORAGE (renumbered as 5.2 )
2.
The following subsections were deleted:
5.1.2 LOW POPULATION ZONE e
5.1.3 SITE BOUNDARY FOR GASEOUS EFFLUENTS-5.1.4 SITE BOUNDARY FOR L10010 EFFLUENTS
-5.2 CONTAINHENT 5.3 REACTOR CORE 5.4 MAIN COOLANT SYSTEM 5.5 METEOROLOGICAL TOWER LOCATION 5.7 C9mPONENT CYCLIC OR TRANSIENT LIMIT keasons and Bases 1.
Design Feature 5.6 was renumbered for ease of use.
No other-changes were made.
2.
The deleted subsections and any corresponding figures address design features associated with fuel 11n the reactor vessel, power operation of the f acility and/or the former full. power emergency plan.
These subsections are not required because the Possession Only License prohibits power operations and prohibits movement of fuel into containment.
Requirements of Specifications 5.1.3.
5.1.4. and 5.5 are and/or will be contained in the-0DCM.-
unn-25 l
-l
Attachment A 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY No change..
6.2 ORGANIZATION Change 1.a.
In Subsection 6.2.2.g. 2nd paragraph, delete the words:
j i
... extended periods shutdowr. for refueling,.. '
1.b.
In Subsection 6.2.2.c(4), delete the words j
- Except during extended shutdown periods,*.
1.c.
Change subsection numbering f rom 6.2.2.g(4) to 6,2.2.f(4)._
l Reason and Basis
(
1.
With the Possession Only License, extended shutdown periods are the norm rather than the exception.
The exception for 6.2.2.f(4) has no meaning and should be deleted for clarity of the remaining specification.
6,3 FACILITY STAFF OlJALIFICATIONS No change.
6.4 TRAINING-1.
Replace subsection 6.4.1 with the new subsection 6.4,1.
Reason and Basis 1.
The new subsection 6.4.1 expands,the description of the training requirements to encompass the training program for the balance of plant staff, as well as the Certified Fuel Handlers.
e t
urau 26 i
Attachmont A 6.5 Rfy]EW AND AUDIT Change 1.
Under the responsibilities of PORC, expand subsection 6.5.1.6.c.
' Review of all changes to the Technical Specifications' to include changes to the License.
Add "Defueled' to describe the Security Plan and Emergency Plan in 6.5.1.6.i and j, respectively.
2.
Modify Specifications 6. :;. 2. 2. 6. 5. 2. 3. 6. 5. 2. 4. 6. 5. 2. 6, a nd 6.5.2.7 to redefine the composition of the Nuclear Safety Audit and Review (NSAR) Committee and quorum reqairements.
3.
In Specification 6.5.2.9.e and 6.5.2.9 f. insert the word
- Def ueled' bef ore Emergency Plan and Security Plan, respectively.
4.
In the following subsections, replace the variout executive titles with the standardized title 'Hanager of Operations":
6.5.2.2 6.5.2.4 6.5.2.8.1 6.5.2.9.1 6.5.2.10 6.5.2.11 5.
Delete Specification 6.5.3.
Reasons and Bases 1.
The change to Specification 6.5.1.6.c reflects the intent of the specification.
The changes to 6.5.1.6 i and 6.5.1.6.j are needed to reflect the fact that NRC reviewed and approved YNP'.' Defueled Security Plan and Defueled Emergency Plan.
These plans are currently in effect.
2.
Specification 6.5.2.2 currently requires that the NSAR Committee be composed of the Chairman and Vice Chairman.
Now that YNPS is permanently shutdown and defueled, and maintenance of the facility has been significantly simplified, six NSAR Committee members are not needed.
The specification hes been changed to require a Chairman and a minimum of four members.
The revised wording continues to maintain the proper and independent perspective by requiring members not to be members of the plant staff.
Specification 6.5.2.3 requires that certain disciplines be represented on the NSAR Committee.
Because the POL prohibits poser operations and transfer of fuel from the spent fuel pit to amen 27
Attachm,ent A the vapor _ container, certain disciplines are no longer _needed.
Reactor operations, utility operations, reactor engineering, and metallurgy have been deleted.
Facility operations and engineering / nuclear engineering have been added.
l Specification 6.5.2.4 imposes requirements on the number of alternates who can participate in NSAR Committee activities.
Since the minimum number of NSAR Committee members has been reduced, the number of alternates has been reduced from two to one to ensure participation of at least two full time members for q
purposes of a quorum, i
Specification 6.5.2.6 imposes HSAR Committee meeting frequency requirements.
This-specification is revised to reflect the change l
made in Specification 6.5.2.2: that is,--the title of 'Vice Chairman' has been deleted. -
Specification 6.5.2.7 provides the definition _of a quorum for the NSAR Committee.
This specification is revised to be consistent with the change made to Specification 6.5.2.2 by requiring a majority of the NSAR Committee members to make up a quorum.
For the same reasons as provided above for Specification 6.5.2.2, there no longer is the need to have as large of an NSAR Committee quorum as was required for power operations.
3.
The changes to Specifications 6.5.2.9.e and 6.5.2.9 f are needed-to reflect the fact that NRC reviewed and approved YNPS' Defueled Emergency Plan and Defueled Security Plan.
These plans-are currently in effect.
4.
This change is for consistency and clarity, since several titles have been used to refer to the same executive within Yankee Atomic Electric Company.
5.
The purpose of the audits required by S'pecifications 6.5.3.1 (annually) and 6.5.3.2 (every 3 years) is to assess the plant fire protection equipment and program implementation in depth to verify continued compliance with NRC requirements, namely 10 CFR 50.16.
10 CFR 50.48 is predicated on the need to ensure that a fire cannot result in the loss of important' safety functions _ such that '
there is a potential for core damage.
- With the plant permanently shutdown and defueled, there no longer
~
is a concern regarding safe shutdown of the reactor.
Furthermore,'
loss of support systems for cooling of the spent fuel' pit will not result in damage to-the spent fuel-that is being stored such_that there would be a. radiological risk to the public, for the following reasons.
Based on the shutdown date of October 1, 1991...
1 nueo 28
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- an evaluation of a-loss of spent fuel pit cooling capability indicates that greater-than three weeks are available to restore spent fuel pit cooling or to establish make-up to replenish spent fuel pit water inventory lost through evaporation.- In addition, initiation of a fire in the. Spent Fuel Building is highly improbable _ due to the minimum combustible loading in the building.
Based on the above reasons, the requirement for a triennial _ audit, which differs from the annual audit only in who conducts the-
)
audit, is no longer needed.
Annual audits and assessments of the Fire Protection Program needed for the permanently shutdown and i
defueled condition will be controlled through administrative procedures.
6.6 REPORTABLE EVEtiT ACT1011 i
No change.
6.7 SAFETY llHIT VIOLATION Change 1.
Section 6.7 SAFETY LIMIT VIOLATION was deleted entirely.
Reason and Basis l
1.
Section 6.7 SAFETY LlHIT VIOLATION addressed issues associated with Section 2.0 of the Technical Specifications, which-was not retained.
This subsection is not required by the Possession Only License for YNPS which prohibits power operations and further prohibits movement'of fuel into the reactor vessel.
6.8 PROCEDURES AND PROGRAMS Renumbered only (new 6.7).
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6.9 REPORTING REQUIREMENTS Chance 1.
Delete Subsection 6.9.1, which refers to Startup Reports.
2.
Delete Subsection 6.9.2.c. which refers to challenges to the PORV.
3.
Delete Subsection 6.9.2.d. which refers to specification 3.4.7,-
primary coolant specific activity.
i 4.
Delete Subsection 6.9.4. which refers to Core Operating limits Report.
5.
- Delete Subsections 6.9.6.c 6.9.6 k. 6.9.6.1, 6.9.6.m. 6.9.6.n-and 6.9.6.o.
6.
Rer' umber the remaining subsections within 6.9 sequentially as subsections 6.8.
Reasons and Bases 1.
Under the Possession Only License, power operations are prohibited and fuel is prohibited from being transferred back into the reactor vessel from the Spent Fuel Pit.
There will be no need for' Startup Reports.
2, Specifications governing the PORV are no longer applicable and would be deleted entirely by the proposals for Specifications 3.4.2 and 3.4.2 contained herein.-
p 3.
Specifications governing the specific activity of the primary coolant are no longer applicable and would be. deleted entirely by the proposals for Specifications 3.4.7 contained herein.
4.
- Under the-Possession Only License, power-operations are prohibited and fuel is prohibited from being transferred back into the reactor vessel from the Spent Fuel Pit.
There will be no.need for Core Operating Limits Reports, f
. 5'. a.
Requirements for control of-the Meteorological. Tower
~
Instrumentation, including reporting, will be transferred to:the ODCM.
5.b.
Specifications governing Radiation Monitoring Reports are no
-longer required. - The Specification.6.9.6.k. applied to the High Range Containment Radiation Monitoring Instrumentation.
This instrumentation was needed for power operations conditions.
Since i
L uneo-30 i
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Attachment A the POL precludes YNPS from power operations and the plant is-permanently defueled, the instrumentation reporting requirements are not needed.
S.c.
Specifications governing structural _ integrity, steam generators, inspections. containment inspections and inoperable explosive gas monitoring instrumentation are no longer applicable and would be deleted entirely by the proposals for Specifications 3.4.9.
3.4.10. 3.6.1.6 and-3.3.3.7 respectively, contained herein.
S.d.
Renumbering the-subsections will improve the clarity of the Technical Specifications.
f.10 RECORD RETENTION Change 1.
Revise wording of Specification 6.10.2.a.
2.
Renumbered (new 6.9).
Reasons and Bases The term
- Final Hazards Summary Report
- is replaced with *FSAR* to-reflect current terminology, ti.11 RADIATION PROTFCTION PROGRAM Renumbered only (new 6.10).
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Attachment A 6,12 HIGH RAD]ATION AREA i
Chance l
1.
Revise the wording of Specification 6.12.
2.
Renumbered (new 6.11).
Reasons and Bases The term ' Health Physics
- is replaced with ' Radiation Protection" to reflect current use of the term. The title ' Plant Health Physicist
- is replaced with ' Radiation Protection Manager.' These changes are only administrative in nature.
6.13 ENVIRONMENTAL 00AllFICATION Chance 1.
Section 6.13 ENVIRONMENTAL QUALIFICATION was deleted entirely.
Reason and Basis 1.
Section 6.13 ENVIRONMENTAL QUALIFICATION addressed the environmental qualification of important-to safety equipment as defined by 10 CFR 50.49.
This regulation,- which is premised on power operations, no longer. applies as the Possession Only License prohibits power operations.
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6.14 PROCESS CONTROL PROGRAM Renumbered only (new 6.12).
6.15 0FF-SITE DOSE CALCULATION MANUAL Renumbered only (new 6.13).
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ATTACHMENT B YANKEE ~ NUCLEAR POWER STATION POSSESSION ONLY LICENSE-PAGES 3:and 4 REVISION
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_t and to the rules,- regulations,-and orders of-the Commission now or hereaf ter?
in effect; and is subject to the additional conditions specified or
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incorporated below:
(1) paximum Power tevel The licensee is not authorized to operate the reactor.
Fuel may i
not'be placed in the reactor vessel.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as_ revised' through Amendment No, are hereby incorporated in the license.
The licensee shall maintain the facility in accordance with the' Technical Specifications.
(3)
Physical Protection The licensee shall fully implement -and maintain in effect all-
. provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans-including amendments made pursuant-to provisions of the Miscellaneous Amendments-and' Search Requirements revision to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans,1which-contain Safeguards Information protected under 10 CFR 72.21, are entitled,-
" Yankee Nuclear Power Station Defueled Security-Plan " Revision 0, dated October-13, 1992 and " Yankee Nuclear Power Station Defueled Security Training and Qualification Plan," Revision 0, dated:
October 13, 1992.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set-forth; therein.
(4)-
Fire Protection The licensee shall_ implement _and maintain in effect -all provisions of the approved Fire Protection Program as described in; the Final. Safety Analysis Report for the facility and as approved' by NRC Safety Evaluation Reports. dated March 15, 1979,-'and as-supplemented October 1, 1980 and AugustL27, 1986,= subject.to'the-
-following-provisions:
The licensee may make changes to the-. approved Fire Protection:
Program' without_- prior NRC approval only if those. changes would not -
adversely. affect the-ability-to maintain tho fuel in the Spent' a
Fuel-Pit in a safe condition in the event of a fire.
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4 (5)-
The movement' of special nuclear ~ material-used as reactor:
'.f uel 4 into'the Vapor Container-(containment) is prohibited.
(6)
The 1icensee shall maintain a Fitness for Duty Program in accordance with the'. requirements of 10 CFR Part 26.
D.
This amended license is effective as of the date of issuance and shall expire at midnight, FOR THE NUCLEAR REGULATORY COMMISSION I
Date of Issuance:
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