B18666, Administrative Error Associated with Tscr 2-2-01 & License Amendment 266

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Administrative Error Associated with Tscr 2-2-01 & License Amendment 266
ML021640234
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/29/2002
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
B18666
Download: ML021640234 (9)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.

i Dominion.....

Millstone Power Station Rope Ferry Road Waterford, CT 06385 MAY 2 g 2002 Docket No. 50-336 B18666 RE: 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attention: Document Control!Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Administrative Error Associated with TSCR 2-2-01 and License Amendment No. 266 In a letter dated June 4, 2001,0) Dominion Nuclear Connecticut, Inc. (DNC) submitted a License Amendment Request to th6 Nuclear Regulatory Commission (NRC) which consisted of the proposed relocation of Millstone Unit No. 2 and Millstone Unit No. 3 Technical Specifications relating to the Reactor Coolant System from each facility's Technical Specifications to their respective Technical Requirements Manuals (TRM).

One of the proposed changes for Millstone Unit No. 2 described within the June 4, 2001, DNC submittal consisted of the relocation of Technical Specification 3.4.11, "Reactor Coolant System Vents" to the facility TRM.

This technical specification requires the submittal of a special report to the NRC if the conditions of the associated action statement cannot be met. Technical Specification 6.9.2, "Special Reports," contains an administrative reference (Technical Specification 6.9.2.m) to the special report identified within the action statements for Technical Specification 3.4.11.

Consistent with the proposed relocation of Technical Specification 3.4.11, deletion of Technical Specification 6.9.2.m was discussed within the June 4, 2001, DNC submittal.

However, marked up and retyped pages showing the deletion of Technical Specification 6.9.2.m were inadvertently omitted from the June 4, 2001, DNC submittal.

In a letter dated May 8, 2002,12) the NRC issued License Amendment No. 266 for Millstone Unit No. 2. This license amendment approved the proposed changes identified (1)

Raymond P. Necci letter to U.S. Nuclear Regulatory Commission, "Millstone Nuclear Power Station, Unit Nos. 2 and 3, Technical Specifications Change Requests 2-2-01 and 3-2-01, Relocation of Selected Technical Specifications Related to the Reactor Coolant System,"

dated June 4, 2001.

(2)

Victor Nerses to J. A. Price, "Millstone Nuclear Power Station, Unit No. 2 and 3 - Issuance of Amendments Re: Relocating Various Reactor Coolant System Technical Specifications to the Respective Unit's Technical Requirements Manual (TAC Nos. MB2273 and MB2240)," dated May 8, 2002.

U.S. Nuclear Regulatory Commission B18666/Page 2 in the June 4, 2001, DNC submittal, including the deletion of the Technical Specification 6.9.2.m.

Since the NRC Safety Evaluation Report for License Amendment No. 266 describes the proposed change to delete Technical Specification 6.9.2.m as an acceptable change, DNC considers this omission to be an administrative error which does not require additional NRC review. DNC regrets any inconvenience this error may have caused. provides the marked up version of the appropriate page of the current Technical Specifications associated with the deletion of Technical Specification 6.9.2.m. provides the retyped page for this Technical Specification.

DNC requests that the NRC issue a correction to Millstone Unit No. 2 License Amendment No. 266 which includes the proposed change discussed herein.

DNC requests that this correction be issued by June 15, 2002, to support the implementation period described within Millstone Unit No. 2 License Amendment No. 266.

There are no regulatory commitments contained within this letter.

If you should have any questions on (860) 440-2080.

the above, please contact Mr. Ravi Joshi at Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

J. Al Site President - Millstone Sworn to and subscribed before me this(9(

day of -M a"

,2002 Nota4r4ublic My Commission expires

___ _/___

Lorde A. Arzamarski Notary Public Commission Expires February 28. 2006 Attachments (2) cc:

See next page

U.S. Nuclear Regulatory Commission B18666/Page 3 cc:

H. J. Miller, Region I Administrator V. Nerses, NRC Project Manager, Millstone Unit No. 3 R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Docket No. 50-336 B18666 Millstone Nuclear Power Station, Unit No. 2 Administrative Error Associated with TSCR 2-2-01 and License Amendment No. 266 Marked Up Pages

REACTOR COOLANT SYSTEM

-).& M March 11, 1999 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one reactor coolant system vent path consisting of at least two valves in series capable of being powered from emergency buses shall be OPERABLE and closed at each of the following locations:

a.

Reactor Vessel head

b.

Pressurizer steam space APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With the Pressurizer vent path inoperable, STARTUP and/or POWER OPERATION may continue provided that i) the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path and ii) one power operated relief valve (PORV) and its associated block valve is OPERABLE; otherwise, restore either the inoperable vent path or one PORV and its associated block valve to OPERABLE status within 30 days, or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the path to OPERABLE status.

b.

With the Reactor Vessel Head vent path inoperable, STARTUP and/or POWER OPERATION may continue provided that the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the Reactor Vessel Head vent path to OPERABLE status within 30 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the path to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1. Verifying all manual isolation valves in each vent path are locked in the open position.
2.

Cycling each valve in the vent path through at least once complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.

3.

Verifying flow through the reactor coolant vent system vent paths during COLD SHUTDOWN or REFUELING.

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. 7?, 77, JZ, jgj, J7, 230

CORE OPERATING LIMITS REPORT (CONT.)

r_*,

.8)

XN-NF-78-44(NP)(A),

"A Generic Analysis of the Control rod Ejection Transient for Pressurized water reactors,"

Exxon Nuclear Company.

9)1 XN-NF-621(P)(A),

"Exxon Nuclear DNB Correlation for PWR Fuel Designs,'" Exxon Nuclear Company.,

10) XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup,"

Exxon Nuclear Company.'

11)

ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," AdvancedNuclear Fuels Corporation.

12)

XN-NF-85-92(P)(A),

"Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results,"

Exxon Nuclear Company..

13)

ANF-89-151(P)(A),

"ANF-RELAP Methodology for Pressurized Water Reactors:

Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation.

14)

EMF-1961(P)(A),

"Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors,"

Siemens Power Corporation.

15)

EMF-2310(P)(A),

"SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP.

c.

The core operating limits shall be determined so that all applicable limits (e.g., -fuel thermal-mechanical

limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
d.

The CORE OPERATING LIMITS

REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall. be submitted to the U.S. Nuclear Regulatory Commission, Document Control

Desk, Washington, D.C.
20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Deleted MILLSTONE - UNIT 2 6-19 Amendment No. J*, J*,

0706 X, 260, MUN'IN131MHILVt WUHIKUL3 uecem~er iv9, zo01

NADIITbATIV CONTROL-ADMINISTRATIVE CONTROLS SPECIAL REPORTS (CONT.)

b.

Deleted C.-

Deleted

d.

ECCS Actuation, Specifications3.5.2 and 3. 5.3.

e.

Deleted

f.

Deleted

g.

RCS Overpressure Mitigation, Specification 3.4.9.3.

h.

Deleted

i.

Degradation of containment structure, Specification 4.6.1.6.4.

j.

Steam Generator Tube Inspection, Specification 4.4.5.1.5.

k.

Accident Monitoring Instrumentation, Specification 3.3.3.8.

1. Radiation Monitoring Instrumentation Specification
m.

Rcacto*, Colan~t Systcm Vcnt*, Specificaion *-3-A.1-*-*....

6.10 Del eted.

Millstone Unit 2 6-20 Amendment No. P, ý# 1f W. 09 9,11WZP

Docket No. 50-336 B18666 Millstone Nuclear Power Station, Unit No. 2 Administrative Error Associated with TSCR 2-2-01 and License Amendment No. 266 Retyped Paqe

ADMINISTRATIVE CONTROLS SPECIAL REPORTS (CONT.)

b.

Deleted

c.

Deleted

d.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e.

Deleted

f.

Deleted

g.

RCS Overpressure Mitigation, Specification 3.4.9.3.

h.

Deleted

i.

Degradation of containment structure, Specification 4.6.1.6.4.

j.

Steam Generator Tube Inspection, Specification 4.4.5.1.5.

k.

Accident Monitoring Instrumentation, Specification 3.3.3.8.

1.

Radiation Monitoring Instrumentation, Specification 3.3.3.1.

m.

Deleted 6.10 Deleted.

Millstone Unit 2 0833 6-20 Amendment No. g, 70, log, 190 Xg, 197, 197, 191, 779,

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