ML20211E776

Amends 130 & 122 to Licenses DPR-42 & DPR-60,respectively, Changing TS Limitations on Crane Operations in SFP Encl Re SFP Special Ventilation Sys Operability

ML20211E776
Person / Time
Site:	Prairie Island
Issue date:	09/15/1997
From:	Wetzel B NRC (Affiliation Not Assigned)
To:
Shared Package
ML20211E780	List: ML20211E776 ML20211E790 ML20211E820
References
NUDOCS 9709300259
Download: ML20211E776 (14)

Text

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UNITE) STATES

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NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D.C. acces-GuH NQRTJERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. 'JNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. DPR-42 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northern States Power Company (the licensee) dated May 7,1997, as supplemented May 30, July 29, and September 12,1997, complies with the standards and requirements of the l

Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules I

and regulations 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 Comrr'ssion's regulations; D.

The issuance of this amendment win not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 2.C.(2) and 2.C.(5) of Facility Operating License No. DPR-42 are here".y amended to read as follows:

9709300259 970915 PDR ADOCK 05000282 P

PDR l

. 1 (2)

' Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(5)

Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.130, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.

3.

This license amendment is effective as of the date of issuance, with full implementation within 30 days. License Condition 4 of Appendix B is effective immediately upon issuance of the amendment.

FOR THE NUCLEAR REGULATORY COMMISSION aa)r Beth A. Wetzel, Senior Project Manager Project Directorate Ill-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation Attachments: 1. Changes to the Technical Specifications

2. Appendix B - Additional Conditions Date of issuance: September 15, 1997

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i ATTACHMENT TO LICENSE AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT TS 3.8-1 TS 3.8-1 TS 3.8-4 TS 3.84 8 3.8-2 8 3.8-2

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'TS.3.8-1 3.8 REFUELING AND FUEL HANDLING

~ hoolicability Applies to operating limitations associated with fuel-handling operations and CORE ALTERATIONS.

Obinetives To eneure that no incident could occur during fuel handling and CORE ALTERATIONS that.would affect public health and safety.

Snecification -

A.

Core Alterations 1.

During CORE ALTERATIONS the following conditions shall be satisfied (except as specified in 3.8. A.2 and 3 below) :

a.

l' Ine equipment hatch shall be closed. In addition, at least one isolation valve shall be OPERABLE or locked closed in each line which penetrates the containment and provides a direct path from containment atmosphere to the outside.

2) Airlock doors a) At least one door in each air lock is closed, or b) Both doors in each air lock may be open if:

1..The containment (high flow) purge system is isolated, ii.~ The inservice (low flow) purge system is capable of automatic isolation, iii.At least one door in each air lock is OPERABLE, under procedural control, and capable of being closed within 30 minutes following a fuel handling accident in

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containment, and 1

.iv. At least two containment fan coil unit fans are capable of operating in the high speed mode following a fuel handling accident in containment.

-b.

-Radiation levels in the fuel. handling areas of-the containment shall.be monitored continuously.

Prairie Island Unit 1.

Amendment No. 91, 119, 130

- Prairie Island Unit 2=

Amendment No. 84, !!2, 122

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3.8.C.

Small Soent Puel Pool Restrictions No more than 45 recently discharged assemblies shall be located in i;-

the small pool (pool No. 1).

D.

Soent Puel Pool Special Ventilation System 1.

Both trains of the Spent ruel Pool Special Ventilation.

System shall be OPERABLE during movement of irradiated fuel assemblies in the spent fuel pool enclosure (except as specified in 3.8.D.2 and 3.8.D.3 below).

2.

With one train of the Spent Puel Pool Special Ventilation System inoperable, fuel handling operations and crane operations with loads over spent fuel (inside the spent fuel pool enclosure) are permissible during the following 7 days, provided the redundant train is demonstrated CPERABLE prior to proceeding with those operations.

3.

With both trains of the Spent Puel Pool Special Ventilation System inoperable, suspend movement'of irradiated fuel assemblies in the spent fuel pool enclosure.

4.

The provisions of specification 3.0.c are not applicable.

E.

gpent Fuel Pool Storace 1.

Fuel Assembly Storage a.

The combination of initial enrichment, burnup and decay time of each fuel assembly stored in the spent fuel pool shall be within the unrestricted range of Figures TS.3.8-1 or TS.3.8-2, as applicable, or fuel assembliea shall-be stored in accordance with Specification 5.6.A.1.o.

b.

If the requirements of 3.8.E.1.a are not met, immediately initiate action to move any noncomplying fuel assembly to an acceptable location.

c.

The provisions of Specification 3.0.c are not applicable.

2.

Spent Puel Pool Boron Concentration The spent fuel pool boron' concentration shall be a 1,800 a.

ppm when fuel assemblies are stored in the spent fuel pool, b.

If the spent fuel pool boron concentration is not within limit, then immediately:

1.

Suspend movement of fuel assemblica in the spent fuel pool, and 2.

Initiate action to restore spent fuel pool boron concentration to within limit.

c.

?The provisions of Specification 3.0.c are not applicable.

Prairie Island Unit 1 Amendment No. &96, 449, 130 Prairie Island Unit 2 Amendment No tek, 444, 122 u.. a e.

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B.3.8-2 3.8 REFUELING AND FUEL HANDLING EAlig continued The Spent Pusi Pool Special Ventilation System (SFPSVS) (Reference 3) is a l

safeguards system which maintains a negative pressure in the spent fuel 1

enclosure upon detection of high area radiation. The Spent Fuel Pool Normal Ventilation System is automatically isolated and exhaust air is drawn through J

filter modules containing a roughing filter, particulate filter, and a charcoal filter before discharge to the environment via one of the Shield Building exhaust stacks.

Two completely redundant trains are provided. The exhaust fan and filter of each train are shared with the corresponding train of the Containment In-service, Purge System. High efficiency particulate i

absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers in each SFPSVS filter train. The charcoal adsorbers are installed to reduce the potential release of radioiodine to the environment.

Doors to the spent fuel enclosure are required to be maintained clo9ed when SFPSVS OPERABILITY is required.

Opening of personnel doors for 1

personnel use is acceptable (blocking a door open is not allowed) (Reference 9).

During movement of irradiated fuel assemblies or control rods, a water level of 23 feet is maintained to provide sufficient shielding.

The water level may be lowered to the top of the RCCA drive shafts for latching and unlatching.

The water level may also be lowered below 20 feet for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to allow time to initiate repairs or emergency procedures to cool the core, (2) during latching / unlatching and upper internals removal / replacement the level is closely monitored because the activity uses this level as a reference point, (3) the time spent at this level is minimal.

The Prairie Island spent fuel storage racks have been analyzed (Reference 8) in accordance with the methodology contained in Reference 5.

That methodology ensures that the spent fuel rack multiplication factor, E(n, is less than 0.95 as recommended by ANSI 57.2-1983 (Reference 6) and NRC guidance (Reference 7).

The codes, methods and techniques contained in the methodology are used to satisfy this criterion on F(n.

The resulting Prairie Island spent fuel rack criticality analysis allows for the storage of fuel assemblies with enrichments up to a maximum of 5.0 weight percent U-233 while maintaining FL,,

0.95 in~1uding uncertainties and credit for soluble boron.

In addition, s

sub-criticality of the pool ( K,,, < 1. 0 ) is assured on a 95/95 basis, without the presence of the soluble boron in the pool. Credit is taken for radioactive decay time of the spent fuel and for the presence of fuel rods containing Gadolinium burnable poison.

The Prairie Island specific criticality analysis (Reference 8) utilized the following storage configurations to ensure that the spent fuel pool will remain saberitical during the storage of fuel assemblies with all possible combinations of burnup and initial enrichment:

Prairie Island Unit 1 Amendment No. 444, 4G9, 130 Prairie Island Unit 2 Amendment No. &&&, 4G+,

122

APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR 42 Northem States Power Company shull comply with the following conditions on the schedules noted below:

Amendment Implementation Number Additional Condition D' te 128

1. NSP will provide a licensed operator in the control Prior to Unit 2 entering room on an interim basis for the dedicated purpose of Mode 2.

identifying an earthquake which results in a decreasing safeguards cooling water bay level. This operator will be in addition to the normal NSP administrative ccatrol room staffing requirements and will be provided until License Condition 2 is satisfied.

128

2. NSP will submit dynamic finite element analyses of the July 1,1997, and intake canal banks by July 1,1997 for NRC review. By December 31,1998, December 31,1998, NSP will complete, as required, as stated in Condition additional analyses or physical modifications which provide 2.

the basis for extending the time for operator post-seismic cooling water load management and eliminating the -

dedicated operator specified in License Condition 1.

128

3. Based on the results of License Condition 2, NSP will At the next USAR revise the Updated Safety Analysis Report to incorporate update following the changes into the plant design bases. These changes completion of will be included in the next scheduled revision of the Condition 2, but no Updated Safety Analysis Report following completion of later than June 1, License Condition 2 activities.

1999.

130

4. Prairie Island will assure that heavy loads do not This is affective present a potential for damaging irradiated fuel through immediately upon use of 1) a single-failure-proof crane with rigging and issuance of the procedures which implement Prairie island commitments amendment.

to NUREG-0612; or 2) spent fuel pool covers with their implementing plant procedures for installation and use.

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UNITED STATES j

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NUCLEAR REGULATORY COMMISSION l

WASHINGTON, D.C. 60001 s,.....f i

NORTilERN STATES PO'NER COMPANY QQQKET NO. 50 3Da PRAIRIE ISLAND NUCLEAR GENERATING, PLANT. UNIT NO. 2 AMENDMENT TO FACILITY.QRE86 TING LICENSE Amendment No.122 Licence No. DPR 60 1.

The Nuclear Regulatory Commission (the Commission) has found tha*:

A.

The application for amendment by Northem States Power Company (the licensee) dated May 7,1997, as supplemented May 30, July 29, and September 12,1997, complies with the standards and requirements of the Abmic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Commisslun; C.

There is reasonable assurance (i) that the activities authorized by this amendmont 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 inimicalin the common defense and security or to the health and safety of the pblic, and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been s:stisfied, 2.

Accordingly, the license is amended by changes to the Technical Specifications an i

indicated in the a'tachment to this license amendment, and paragraphs 2.C.(2) ar$d 2.C.(5) of Facility Operating License No. DPR 60 are hereby amended to read as

- follows:

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Technical Soecifications (2)

The Technical SpecWications contained in Appendix A, as revised through Amendment No.122, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(5)

Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No.122, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions.

3.

This license amendment is effective as of the date of issuance, with full imp 4 mentation within 30 days. License Conditun 4 of Appendix B is effective immediately upon issuance of the amendment.

FOR THE NUCLEAR REGULATORY COMMISSION t

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Beth A. Wetzel, Senior Project Managar Proiect Directorate lil 1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Ntachments: 1. Changes to the Technical Specifications

2. Appendix B - Additional Conditions Date of issuance: Sept. ember 15, 1997

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4 ATTACHMit(I TO LICENSE AMENDMENT NO.122 FACILITY OPERATING LICENSE NO. DPR40 DOCKET. NO, 50-306 Revise AppendW A Technical Specifications by removing the pages identifed below and inseding the attached pages. The revised pages are identifed by amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT TS 3.81 TS 3.81 TS3.84 TS 3.84 0 3.8 2 B 3.8 2 I

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3.8 REFUELIIIG AND FUEL MAltDLilfG I

Annlicability l

Applies to operating limitations associated with fuel-handling operations and CORE ALTERATICIts.

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To ensure that no incident could occur during fuel handling and CORE.

ALTERAT10008 that would affect public health and safety.

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Core Alterations 1.

During CORE ALTERAT20sts the following conditions shkil be satistled i

(except as specified in 3.0.A.3 and 3 below):

a.- 1) The equipment batch shall be closed. In addition, at least one isolation valve shall be OPERABLE or locked closed in each line which penetrates the containment and provides a direct path from containment atmosphere to the outside.

-2) Air?ock doors al At least one door ineesch air lock is closed, or b) Both doors in each air lock may be open if a

i. The containment (high flow) purge system is isolated, ii. The inservice (low flow) purge system is capable of automatic isolation, i

lii.At least one door in each air lock is OPERABLE, under procedural control, and capable-of being closed within 30 minutes following a fuel handling accident in containment, and I

Av. At least two coatsinment ian coil unit ians are capable of operating in the high speed mode followirg a fuel handling accident in containment.

b.

Radiation levels in the fuel handling areas of the containment shall be monitored continuously.

- Prairie Island Unit 1 Amendment No. 91, 119. 130 Prairie _ Island Unit 2 Amendment No. N, = !!!,122 9

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i No more than 45 recently discharged assemblies shall be located in the small pool (pool No.1).

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scant Puni pool snacini ventilation avatam f

i 1.

Both trains of the Spent Puol Pool Special Ventilation System shall be OPERABLE during movement of irradiated fuel assemblies in the spent fuel pool enclosure (except as specified in 3.8.D.2 and 3.8.D.3 below).

2.

With one train of the Spent Fuel Pool Special Ventilation System inoperable, fuel handling operations and crane operations with loads over spent fuel (inside the spent fuel pool enclosure) are permissible during the following 7 days, provided the redundant train is demonstrated OPERABLE prior to proceeding with those operations.

3.

With both trains of the spent Puel Pool Special Ventilation System inoperable, suspend movement of irradiated fuel assemblies in the spent fuel pool enclosure.

4.

The provisions of specification 3.0.C are not applicable.

E.

Boant Puel Pool Storace_

1.

Puel Assembly Storage The combination of initial enrichment, burnup and decay a.

time of each fuel assembly stored in the spent fuel pool shall be within the unrestricted range of Figures 78.3.81 or T8.3.8 2, as applicable, or fuel assemblies shall be stored in accordance with Specification 5.6.A.1.e.

b.

If the requirements of 3.8.E.1.a are not met, immediately initiate action to move any nonconplying fuel assembly to an acceptable location.

c.

The provisions of Specification 3.0.C are not applicable.

2.

Spent Fuel pool Boron concentration a.

The opent fuel pool boron concentration shall be e 1,800 ppm when fuel assemblies are stored in the spent fuel pool.

b.

If the opent fuel pool boron concentration is not within limit, then immediately:

1.

Suspend movement of fuel assemblies in the spent fuel pool, and 2.

Initiate action to restore spent fuel pool boron concentration to within limit.

c.

The provisions of Specification 3.0.c are not applicable.

Prairie Island Unit 1 Amendment No. 444, 449, 130 Prairie Island Unit 2 Amendment No. 666, 44+, 122 4A-

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3.3.8 2 3.8 REPUELING AND FUEL MANDLING P

Stasa continued The spent Fuel pool special Ventilation System (SFPSYS) (Reference 3) is a l

l safeguards system which maintains a negative pressure in the spent fuel enclosure upon detection of high area radiation. The spent Puol Pool Normal Ventilation system is automatically isolated and exhaust air is drawn through filter modules containing a roughing filter, particulate filter, and a t

charcoal filter before discharge to the environment via one of the Shield Suilding exhaust stacks. Two cosylotely redundant trains are provided. The exhaust fan and filter of each train are shared with the corresponding train of the Containment 2n service, Purge System. Migh officioney particulate j

absolute (MEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers in each SFPSVS filter train. The charcoal adsorbers are installed to reduce the potential release of radiciodine to the environment. Doors to the spent fuel enclosure are required to be maintained i'

closed when SFPSYS OPERASILITY is required. Opening of personnel doors for persoranel use is acceptable (blocking a door open is not allowed) (Reference 9).

During movement of irradiated fuel assemblies or control rods, a water level i

of 23 feet is maintained to provide sufficient shielding.

The water level may be lowered to the top of the RecA drive shafts for latching and unlatching. The water level may also be lowered below 20 feet-for upper internals removal / replacement. The basis for these allowance (s) are (1) the refueling cavity pool has sufficient level to allow time to initiate repairs or emergency procedures to cool the core, (2) during latening/unistching and upper internals removal / replacement the level is closely monitored because the activity uses this level as a reference point, (3) the time spent at this level is alnimal.

The Prairie Island spent fuel storage racks have been analysed (Reference 8) in accordance with the methodology contained in Reference 5.

That methodou-*

ensures that the spent fuel rack multiplication factor, N,,,

is less that as recommended by ANSI 57.2-1983 (Reference 6) and NRC guidance (Referens The codes, methods and techniques contained in the methodology are used to satisfy this criterion on M.,E.

The resulting Prairie Island spent fuel rack criticality analysis allows or the storage of fuel assemblies with enrichments up to a maximum of 5.0 weight percent U 235 while maintaining N,,

s 0.95 including uncertainties and credit for soluble boron. In addition, 1.0) is assured on a 95/95 basis without sub criticality of the pool (N,, <in the pool, the presence of the soluble boron credit is taken for radioactive decay time of the spent fuel and for the presence of fuel rods containing Gadolinium burnable poison.

The Prairie Island specific criticality analysis (Reference s) utilised the following storage configurations to ensure that the opent fuel pool will remain subcritical during the storage-of fuel assemblies with all possible combinations of burnup and initial enrichment:

Prairie Island Unit 1 Amendment No. H e, 464, 130 Prairie Island Unit 2 Amendment No. M G, 446, 122 i

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APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Northem States Power Company shall comply with the following conditions on the schedules noted below; Amendment implementation Number 6dditional Condition Date 120

1. NSP will provide a licensed operator in the control Prior to Unit 2 entering room on an intorim basis for the dedicated purpose of Mode 2.

Ide%ing an earthquake which results in a decreasing safeguards cooling water bay level. This operator will be in addition to the normal NSP administrative control room staffing requirements and will be provided until License Condition 2 is satisfied.

120

2. NSP will submit dynamic finite element analyses of the July 1,1997, and intake canal banks by July 1,1997 for NRC review. By December 31,1998, December 31,1998, NSP will complete, as required, as stated in Condition additional analyses or physical modifications which provide 2.

the basis for extending the time for operator post seismic cooling water load management and eliminating the dedicated operator specified in License Condition 1, 120

3. Based on the results of License Condition 2, NSP ' vill At the next USAR revise the Updated Safety Analysis Report to incorporate update following the changes into the plant design bases. These changes completion of will be included in the next scheduled revision of the Condition 2, but no Updated Safety Analysis Report following completion of later than June 1, License Condition 2 activities.

1999.

122

4. Prairie Island will assure that heavy loads do not This is effective present a potential for damaging irradiated fuel through immediately upon use of 1) a single failure proof crane with rigging and issuance of the procedures which implement Prairie Island commitments amendment.

to NUREG-0612; or 2) spent fuel pool covers with their implementing plant procedures for installation and use.

This is effective immediately upon issuance of the amendment.

4

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