PLA-5520, Supplement to Proposed Amendment No. 211 to Unit 2 License NFP-22: MCPR Safety Limits and Reference Changes

Supplement to Proposed Amendment No. 211 to Unit 2 License NFP-22: MCPR Safety Limits and Reference Changes

ML023100301
Person / Time
Site:	Susquehanna
Issue date:	10/30/2002
From:	Shriver B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5520
Download: ML023100301 (12)

Text

Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3120 Fax 570 542.1504 blshfiver@pplweb com

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TM 0 CT 3 0 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT TO PROPOSED AMENDMENT NO. 211 TO UNIT 2 LICENSE NFP-22: MCPR SAFETY LIMITS AND REFERENCE CHANGES PLA-5520 Docket No. 50-388

Reference:

1) PLA-5467, B. L. Shriver (PPL) to USNRC, "Proposed Amendment No. 211 to Unit 2 Licensee NPF-22: MCPR Safety Limits and Reference Changes ", dated July 17, 2002.

2) PLA-5509, B. L. Shriver (PPL) to USNRC, "Supplement to Proposed Amendment No. 243 to License NFP-14 and Proposed Amendment No. 207 to License NFP-22: Adoption of NRC Approved Generic Changes to Improved Technical Specifications ". dated August 23, 2002.

The purpose of this letter is to submit updated Technical Specification markup pages to Section 5.6.5, submitted by Reference 1, which contained the Unit 2 Cycle 12 MCPR Safety Limit Technical Specification change. This update was made necessary by PPL's August 23, 2002 submittal of Reference 2, which provides supplemental information and a revision to the October 16, 2001 submittal of Technical Specification Section 5.6.5 references. These changes are necessary for the NRC staff to complete its review of the license amendment proposed in Reference 1. These changes do not affect the No Significant Hazards Determination submitted with Reference 1. They were identified and discussed during a telecon between PPL and NRC on July 31, 2002. The markups provided are of the Technical Specification Section 5.6.5 pages included in Reference 2.

Document Control Desk PLA-5520 to this letter contains the Technical Specification page markups and includes new camera-ready pages as requested.

Also included are camera-ready pages containing Technical Specification Section 5.7.

These pages have been revised only to consolidate blank space that would otherwise unnecessarily exist. The content of Section 5.7 has not changed.

Should you have any questions or require additional information, please contact Mr. Duane L. Filchner at (610) 774-7819.

Sincerely, B. L. Shriver Attachments:

Affidavit - Markups and Camera-Ready Pages copy: NRC Region I Mr. S. Hansell, NRC Sr. Resident Inspector Mr. T. G. Colburn, NRC Sr. Project Manager Mr. R. Janati, DEP/BRP Mr. E. M. Thomas, NRC Project Manager to PLA-5520 PLA-5509 Markups and Camera-Ready Pages

BEFORE THE BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of PPL Susquehanna, LLC:

Docket No. 50-388 SUPPLEMENT TO PROPOSED AMENDMENT NO. 211 TO UNIT 2 LICENSE NFP-22: MCPR SAFETY LIMITS AND REFERENCE CHANGES Licensee, PPL Susquehanna, LLC, hereby files a revision to its Facility Operating License No. NPF-22 dated March 23, 1984.

This amendment involves a revision to the Unit 2 Technical Specifications.

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"V PPL Susquehanna, LLC B. ý. Slnd NOver Sr. Vice President and Chief Nuclear Officer Sworn to and subscribed before me this 3O day of ODa.-Q.', 2002.

Notary Public Notarial Seal Laurie Minto. Notary Public Salem Twp.. Luzerne County My Commission Expires July 24. 2006 MeMber, Penn syva Assoclalon Notaries

S.Reporting Requirements "5.6 5.6 Reporting Requirements (continued) core thermal power level may not exceed the originally approved.RTP of 3441 MWt, but the value of 3510 MWt (102%

of 3441 MWt) remains the initial power level for the bounding licensing analysis.

Future revisions of approved analytical methods listed in this Technical Specification that are currently referenced to 102% of rated thermal power (3510 MWt) shall include reference that the licensed RTP is actually 3489 MWt.

The r-eyj

.re

• ns__s ho))_documentithiaLtheLi-cen sing analysis performed at 3510 MWt bounds operation at the RTP of 3489 MWt so long as the LEFM/P system is used as the feedwater flow measurement input into the core thermal power calculation.

The -apo-v-ed inalytic-al e'ihobds aie described' in the following documents, the approved version(s) of which are specified in the COLR.

1.

PL-NF-90-O01-A, "Application of Reactor Analysis Methods for BWR Design and Analysis."

2.

XN-NF-80-19(P)(A),

"Exxon Nuclear Methodology for Boiling Water Reactors," Exxon Nuclear Company, Inc.

3-XN-NF-85-_97(PA),

"Generic Mechanical Design for Exxon-Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.

4.

ANF-524(P)(A),

"Advanced Nuclear Fuel sCorporation Criftcai Power Method6o6gy for Boiling Water Reactors."

5 Aj~fl1125(P)A). "f.4F4Citc3 Poweor Corr.4lation A.

NEDC 327P ~'FRGSR l ess.

o of Coolant Arrirdpnt Ana3ysjsK" rE Nmr i

Fnpýoy gy 5 7-NE-092-O01A, "Licensing Topical Report for Power Uprate-Wi t-h-I-ncreas ed-Core -Flow -"-Pennsyivanl a-Power &

Light Company.

8.

Ph NF 94 005 P A. "Teehnical Basiz for SPC 94-i2 Extended Fuel Expesure at Susquehanna SES."

(continued)

SUSQUEHANNA - UNIT 2 Amendment TS / 5.0-22

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

9.

UrrE 24011 P A 10.,CcGRein

[Fle,,tr,,

Application For Reactor Fu...

standr~dn i-.

ANF-89-98(P)(A),

"Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation.

9

+1-.

ANF-91-048(P)(A),

"Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Eva -uat*-on-Model."

12.

XN NF 80 19(P)(A)l "Emmon Nuclear Met, It "1A

+

n M+..-

delegy for NNF.-...XN-NF.-7g-_71(P)_(A),

"-Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors."

91 4+. EMF-1997 (P)(A),

"ANFB-10 Critical Power Correlation."

10 -¶-5-.

Caldon, Inc., "TOPICAL REPORT:

Power Accuracy and Plant Safety Operating Power Level Using the Engineering Report - 80P.

Improving Thermal While Increasing LEFM/IN System,".

Caldon, Inc., "Supplement to Topical Report ER-80P:

Basis for a Power Uprate with the LEFM/w or LEFN

_CheckPlusT-System, -"Engineering Report ER-160P."

---2-*A---.-EMrF-85-74P, "RODEX 2A (BWR)

Fuel Rod Thermal S..

..... Mechani caL

-Eva l-uati on-Model-."

.c.

The-core operating limits shall be determined-such applicable limits (e.g., fuel thermal mechanical lii core thermal hydraulic limits, Emergency Core Cooli Systems (ECCS) limits, nuclear limits such as SDM, analysis limits, and accident analysis limits) of t analysis are met.

d.

The COLR, including any midcycle revisions or suppl shall be provided upon issuance for each reload cyc NRC.

that all

mfts, ng transient he safety

ements, le to the Pvs 0

/M

• *,o I

continued; SUSQUEHANNA - UNIT 2 I

I I

.8 TS / 5.0-23 Amendment

Reporting Requirements 5.6 5.6 Reporting Requirements core thermal power level may not exceed the originally approved RTP of 3441 MWt, but the value of 3510 MWt (102% of 3441 MWt) remains the initial power level for the bounding licensing analysis.

Future revisions of approved analytical methods listed in this Technical Specification that are currently referenced to 102% of rated thermal power (3510 MWt) shall include reference that the licensed RTP is actually 3489 MWt.

The revisions shall document that the licensing analysis performed at 3510 MWt bounds operation at the RTP of 3489 MWt so long as the LEFMV"TM system is used as the feedwater flow measurement input into the core thermal power calculation.

The approved analytical methods are described in the following documents, the approved version(s) of which are specified in the COLR.

1.

PL-NF-90-001 -A, "Application of Reactor Analysis Methods for BWR Design and Analysis".

2.

XN-NF-80-19(P)(A), "Exxon Nuclear Methodology for Boiling Water Reactors" Exxon Nuclear Company, Inc.

3.

XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, "Exxon Nuclear Company, Inc.

4.

ANF-524(P)(A), "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors".

5.

NE-092-001A, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company.

6.

ANF-89-98(P)(A) "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation.

7.

ANF-91-048(P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model."

8.

XN-NF-79-71 (P)(A) "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors."

9.

EMF-1 997 (P)(A) "ANFB-1 0 Critical Power Correlation."

10.

Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM VTM System," Engineering Report - 80P.

(continued)

SUSQUEHANNA - UNIT 2 Amendment TS / 5.0-22

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

11.

Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMVTM or LEFM CheckPlusTM System, "Engineering Report ER-160P.

12.

EMF-85-74 (P)(A), "RODEX 2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model."

13.

EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2,"

Siemens Power Corporation.

c.

The core operating limits shall be determined such that all applicable limits (e.g.,

fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 EDG Failures Report If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experienced by that EDG in that time period shall be reported within 30 days.

Reports on EDG failures shall include the information recommended in Regulatory Guide 1.9, Revision 3, Regulatory Position C.4.

5.6.7 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

SUSQUEHANNA - UNIT 2 TS / 5.0-23 Amendment

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7 Hi-gh Radiation Areas As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:

5.7.1 Hi-gh Radiation Areas with Dose Rates Less than or equal to 1.0 rem/hour at 30 Centimeters from the Radiation Source or from Any Surface Penetrated by the Radiation:

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures (e.g., radiation protection technicians) and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

(i)

A radiation monitoring device that continuously displays radiation dose rates in the area; or (ii)

A radiation monitoring device, with an appropriate alarm setpoint, that continuously integrates the radiation dose rates in the area and alarms when the devices's dose alarm setpoint is reached or (iii)

A radiation monitoring device that continuously transmits dose rate and cumulative dose to a remote receiver monitored by radiation protection (continued)

SUSQUEHANNA - UNIT 2 Amendment TS / 5.0-24

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 (continued) personnel responsible for controlling personnel radiation exposure within the area, or (iv) A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area.

e. Except for individuals qualified in radiation protection procedures, or individuals escorted by personnel qualified in radiation protection procedures, entry into such areas shall be made only after dose rates in the area have been evaluated and entry personnel are knowledgeable of them.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Source or from Any Surface Penetrated by the Radiation, but Less Than 500 rads/hour at 1 Meter from the Radiation Source or from Any Surface Penetrated by the Radiation:

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked door or gate that prevents unauthorized entry, and, in addition:

(i)

All such door and gate keys shall be maintained under administrative control of the shift supervisor, radiation protection manager, or his designee.

(ii)

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

(continued)

SUSQUEHANNA-UNIT2 TS / 5.0-25 Amendment

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual (whether alone or in a group) entering such an area shall possess:

(i)

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or (ii)

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (iii)

A self reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (a)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (b)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or, (continued)

SUSQUEHANNA - UNIT 2 TS / 5.0-26 Amendment

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)

(iv) In those cases where options (ii) and (iii), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area may be used.

e. Except for individuals qualified in radiation protection procedures, or individuals escorted by personnel qualified in radiation protection procedures entry into such areas shall be made only after dose rates in the area have been evaluated and entry personnel are knowledgeable of them.

f. Such individual areas that are within a larger area that is controlled as a high radiation area, where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, but shall be barricaded and conspicuously posted as a high radiation area, and a conspicuous, and clearly visible flashing light shall be activated at the area as a warning device.

SUSQUEHANNA - UNIT 2 TS / 5.0-27 Amendment