ML070090485

Perry Nuclear Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process

ML070090485
Person / Time
Site:	Perry
Issue date:	12/29/2006
From:	Pearce L W FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PY-CEI/NRR-2995L
Download: ML070090485 (10)

Text

FENOC Perry Nuclear Power Station 10CetrRa FirstEnergy Nuclear Operating Company Perry, Ohio 44081 L. William Pearce 440-280-5382 Vice President Fax: 440-280-8029 December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CE I/N RR-2995L 10 CFR 50.90 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Perry Nuclear Power Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, 'Scram Discharge Volume (SDV) Vent and Drain Valves," Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, the FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications (TSs) for the Perry Nuclear Power Plant.The proposed changes would revise the Required Action in TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable.

These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor (BWR) BWR6 Standard Technical Specification NUREG-1434.

The availability of this TS improvement was announced in the Federal Register on April 15, 2003, as part of the Consolidated Line Item Improvement Process (CLIIP).Enclosure 1 provides a description of the proposed change and confirmation of applicability, the existing TS pages marked-up to show the proposed change, and the existing TS Bases pages marked-up to reflect the proposed change (for information only). There are no new regulatory commitments associated with this proposed change.Approval of the license amendment is requested prior to December 30, 2007, with the amendment to be implemented within 90 days following its effective date.In accordance with 10 CFR 50.91, a copy of.this application, with enclosure, is being provided to the designated State of Ohio Official.

December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CEI/N RR-2995L Page 2 of 2 If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at 330-315-7243.

I declare under penalty of perjury that the foregoing is true and correct. Executed on December 29, 2006.Enclosure.

1. Perry Nuclear Power Plant Evaluation for a Proposed License Amendment to Revise Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves" cc: NRC Project Manager NRC Resident Inspector NRC Region Ill N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Enclosure 1 PY-CEI/N RR-2995L Page 1 of 3 PERRY NUCLEAR POQWER PLANT EVALUATION FOR A PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 3.1.8, "SCRAM DISCHARGE VOLUME (S DV) VENT AND DRAIN VALVES"

1.0 DESCRIPTION

OF PROPOSED AMENDMENT 2.0 ASSESSMENT

2.1 APPLICABILITY

OF PUBLISHED SAFETY EVALUATION

2.2 OPTIONAL

CHANGES AND VARIATIONS

3.0 REGULATORY

ANALYSIS 3.1 NO SIGNIFICANT HAZARDS CONSIDERATION

3.2 VERIFICATION

AND COMMITMENTS

4.0 ENVIRONMENTAL

EVALUATION

7.0 ATTACHMENTS

1. Proposed Operating License Change (Hand Mark-up)2. Proposed Technical Specification Bases Changes (For Information Only)

Enclosure 1 PY-CEI/NRR-2995L Page 2 of 3

1.0 DESCRIPTION

OF PROPOSED AMENDMENT The proposed license amendment would revise Required Action in Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable.

These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor 6 Standard Technical Specifications, NUREG-1434.

The availability of this Technical Specification improvement was announced in the Federal Register on April 15, 2003 (68 FR 18294) as part of the Consolidated Line Item Improvement Process (OLIIP). Refer to Attachment 1 for a mark-up of the existing TS reflecting the proposed changes.2.0 ASSESSMENT

2.1 Applicability

of Published Safety Evaluation FirstEnergy Nuclear Operating Company (FENOC) has reviewed the NRC safety evaluation published on April 15, 2003 (68 FR 18294) as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the information provided to support TSTF-404.FENOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the Perry Nuclear Power Plant (PNPP)and justify this amendment for the incorporation of the changes into the PNPP Technical Specifications.

2.2 Optional

Changes and Variations FENOC is not proposing any variations or deviations from the Technical Specification changes described in TSTF-404 or the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).3.0 REGULATORY ANALYSIS 3.1 No Significant Hazards Consideration FENOC has reviewed the proposed no significant hazards consideration determination published on April 15, 2003 as part of the CLIIP. FENOC has concluded that the proposed determination presented in the notice is applicable to PNPP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).3.2 Verification and Commitments There are no new regulatory commitments associated with this proposed change.4.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model safety evaluation published on April 15, 2003, as part of the CLIIP. FENOC has concluded that the NRC staff's Enclosure 1 PY-CEI/NRR-2995L Page 3 of 3 findings presented in that evaluation are applicable to PNPP and the evaluation is hereby incorporated by reference for this application.

5.0 PRECEDENT

This application is being made in accordance with the OLIIP. FENOC is not proposing variations or deviations from the Technical Specification changes described in the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).Similar changes to Technical Specification SDV ACTIONS were approved by the NRC for the Pilgrim Nuclear Power Station (TAC NO. MC5422 -ADAMS Accession Number ML051870257) dated July 29, 2005; and for the Hope Creek Generating Station (TAC NO. MC6697 -ADAMS Accession Number ML060050304) dated January 13, 2006.

6.0 REFERENCES

1. Federal Register, "Notice of Availability of Model Application Concerning Technical Specifications Improvement Regarding Scram Discharge Volume Vent and Drain Valves Actions for Boiling Water Reactors Using the Consolidated Line Item Improvement Process," April 15, 2003 (68 FR 18294)2. Technical Specifications Task Force (TSTF) Change Traveler 404, Revision 0 7.0 ATTACHMENTS

1. Proposed Operating License Change (Hand Mark-up)2. Proposed Technical Specification Bases Changes (For Information Only)

Attachment 1 PY-CE I/N RR-2995L Page 1 of 2 PROPOSED OPERATING LICENSE CHANGE (HAND MARK-UP)

Attachment 1 PY-C EI/N RR-2995L Page 2 of 2 SDV Vent and Drain Valves 3.1 RECIIYCONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent ah'd Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE.APPLICABILITY:

MODES I and 2.ACTIONS--------------------------

--NOTE--/ý-------------------------------

t~Se arate Condition entry is allowe S DV vent and drain line.-- ------------------------

---

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Rftzt-oe mlV~ " ti 7 days or drain lines with OPERADLE status.one valve inoperable.

1oUr T)-h /45c;B. One or more SDV vent B.1 --or drain lines with -Aýn isolated line may both valves be unisolated under inoperable, administrative control to allow draining and venting Isolate the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated line.C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion.Time not met.PERRY -UNIT*1 3.1-24 PERR -NIT 3.-24Amendment No. 69 Attachment 2 PY-CEI/NRR-2995L Page 1 of 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES.(FOR IN FORMATION ONLY)

Attachment 2 PY-CEIINRR-2995L Page 2 of 3 SDV Vent and Drain Valves B 3.1.8 INFOR" AT10DOJ liLL BAS ES APPLICABLE SAFETY ANALYSES (continued) allow continuous drainage of the SDV during normal plant operation to ensure the SDV has sufficient capacity to contain the reactor coolant discharge during a full core scram. To automatically ensure this capacity, a reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS)Instrumentation")

is initiated if the SDV water level exceeds a specified setpoint.

The setpoint is chosen such that all control rods are inserted before the SDV has insufficient volume to accept a full scram.SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement.

LCO The OPERABILITY of all SDV vent and drain valves ensures that, during a scram, the SDV vent and 'drain valves will close to contain reactor water discharged to the SDV piping.Since the vent and drain lines are provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to be open to ensure that a path is available for the SDV piping to drain freely at other times.APPLICABILITY In MODES 1 and 2. scram may be required, and therefore, the SDV vent and drain valves must be OPERABLE.

In MODES 3 and 4. control rods are not able to be withdrawn since the reactor mode switch is in the shutdown position and a control rod block is applied. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies.

Therefore, the SDV vent and drain valves are not required to be OPERABLE in these MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram.ACTIONS The ACTIONS table is modified by/ANoteyindicating that a separate Condition entry is allowed for each SDV vent and drain line. This is acceptable, since the Required Actions*for each Condition provide appropriate compensatory actions xk"s-P'U URDV for each inoperable SDV line. Complying with .the Required Fam IN OR IA INActions may allow for continued operation, and subsequent Po E3J'I-47 inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.p.

y ~(conti nued)PFRRY -UNIT 1B31-6Rvso No 1 B 3.1-46 Revision No. I Attachment 2 PY-CEI/NRR-2995L Page 3 of 3 IN I 0 ATI ,0 him 0N I. YSDV Vent and Drain Valves B 3.1.8 BASES ACTIONS A.1 the reacfcp cccJ4?i,0 cir ~CiV.":; r" ,(cotined)

When one SDV vent or drain valve is inoperable in one o more lines, the ,avzmtbortrdtoOEABE ttu-w-i 4---ds The-pCompletion Time is reasonable, given the ,--7ev-e-Fof--re-du-ndancy in the lines and the ]ow~probability of a scram occurring during the time the valve(s) are inooerabL1e The SDV is still isolable since the redundant valve in the affected line is OPERABLE.

Since the SDV is anct &he- h4i still isolable, the affected SDV line may be opened. This no,+~ isclcte~d-allows any accumulated water in the line to be drained, to preclude a reactor scram on SDV high level. During these periods, the single failure criterion may not be preserved, and a higher risk exists to allow reactor water out of the primary system during a scram.B.1 If both valves in a line are inoperable, the line must be isolated to contain the reactor coolant durnn control Thinei ,salowsany ccuulaed atr ian therSVtobe dr~ained to preclud a reacto isicreamnsedV.

ihlvl Thea 8dhurCmlto Tie to hgSD ee isolcrated thriei aed, o thelowproabiityof scam ccurin whleDheringteise nerots telnmabeuisolatedad unliklioo ofsgiiadmntsCratisea leakage Ifonyrl Reqire actions and associlated Competion time isD notb mriet, the plantlustde broughttor scam MoDin which thevelCD does not accppaly.

Toiachee the disistratusvte plantrmust bensr if ~ ~ ~ ~ ~ ~ ~ ~ (ot anued)cr wt heln ntioltd IN OR AT O 0 LYrCmlto iet soaeteln sbsdo PERRY -UNIT 1B31-7RvsoN.1 B 3.1-47 Revision No. I