ML14176A527

Summary of 900824 Meeting W/Util to Discuss Various Aspects of Licensing Process & Submittals

ML14176A527
Person / Time
Site:	Harris, Brunswick, Robinson
Issue date:	12/06/1990
From:	Adensam E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9012120360
Download: ML14176A527 (19)

Text

N9 REGu UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 6, 1990 Docket Nos. 50-325/324 50-261 50-400 LICENSEE:

CAROLINA POWER & LIGHT COMPANY FACILITIES: BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1

SUBJECT:

MEETING

SUMMARY

OF AUGUST 24, 1990 WITH CAROLINA POWER & LIGHT COMPANY REGARDING THE REGARDING LICENSING PROCESS On August 24, 1990, members of the NRC staff met with Carolina Power & Light

. Company (CP&L) licensing staff to discuss various aspects of the licensing process and submittals. Specifically, the intent of the meeting was to exchange ideas and views on formatting Technical Specification (TS) change submittals to reduce efforts by both the licensee and the NRC staff and simplify the process. A list of attendees is provided in Enclosure 1. provides the agenda discussed, and Enclosure 3 is a copy of the viewgraphs used and examples discussed during the meeting.

Patricia Anderson, Licensing Assistant with the NRC staff, explained the process the NRC staff uses in issuing amendments and identified areas where the licensee could modify its practices for submittals and help the staff expedite their work. Bill Murray of the licensee's staff covered the process CP&L uses in developing applications for amendments. An open dialogue developed several questions that the NRC staff was to take under advisement as follows:

1. The NRC staff would identify to the licensee those Sholly evaluations that were either more detailed than required or not adequate enough for the staff to use without some modification.

2. Because CP&L provides the final TS pages for issuance with the amendment, the NRC staff would advise the licensee when to submit "clean" TS pages.

3. The NRC staff would check with the Robinson PM to determine whether or not the staff was receiving good quality copies of the TS pages for issuance with the amendment package.

4. The NRC staff would consult with the Office of the General Counsel (OGC) regarding the nature of responses to requests for additional information related to an amendment, i.e., do these responses constitute part of the amendment request regardless of content?

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5. The NRC staff would provide guidance to the licensee regarding timing for changing Bases pages in their TS.

Other issues discussed were resubmittal of Sholly notice information supporting changes to an amendment request, placement of change bars on figures in the TS, document control methodologies, electronic storage planned by the licensee, and what was expected by the staff regarding the implementation date included in license amendments.

Original Signed By:

Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects -

I/II

Enclosures:

As stated cc w/enclosures:

See next page DISTRIBUTION See attached page OEC

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I-1 NAME

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12/&/90

12/

/90 OFFICIAL RECOR COPY Document Name:

CP&L AUGUST MTG

SUMMARY

Mr. L. W. Eury Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. Russell B. Starkey, Jr.

Mr. H. A. Cole Vice President Special Deputy Attorney General Brunswick Nuclear Project State of North Carolina P. 0. Box 10429 P. 0. Box 629 Southport, North Carolina 28461 Raleigh, North Carolina 27602 Mr. R. E. Jones, General Counsel Mr. Robert P. Gruber Carolina Power & Light Company Executive Director P. 0. Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 P. 0. Box 29520 Raleigh, North Carolina 27626-0520 Ms. Frankie Rabon Board of Commissioners P. 0. Box 249 Bolivia, North Carolina 28422 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 P. 0. Box 208 Southport, North Carolina 28461 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environmental, Commerce and Natural Resources P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Mr. J. L. Harness Plant General Manager Brunswick Steam Electric Plant P. 0. Box 10429 Southport, North Carolina 28461

Mr. L. W. Eury Carolina Power & Light Company Shearon Harris cc:

Mr. R. E. Jones, General Counsel CarolinaU.S.

Nuclear Regulatory Commission P. 0. Box 1551 101 Marietta Street Raleigh, North Carolina 27602 Suite 2900 Resident Inspector/Harris NPS c/o U. S. Nuclear Regulatory Commission Mr. C. S. Hinnant Route 1, Box 315B Plant General Manager New Hill, North Carolina 27562 Harris Nuclear Plant P. 0. Box 165 Mr. R. B. Richey, Manager New Hill, North Carolina 27562 Harris Nuclear Project Harris Nuclear Plant Mr. Dayne H. Brown, Director P. 0. Box 165 Division of Radiation Protection New Hill, North Carolina 27562 N. C. Department of Environmental, Commerce & Natural Resources Mr. H. A. Cole P. 0. Box 27687 Special Deputy Attorney General Raleigh, North Carolina 27611-7687 State of North Carolina P. 0. Box 629 Raleigh, North Carolina 27602

Mr. L. W. Eury H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:

Mr. R. E. Jones, General Counsel Mr. Dayne H. Brown, Director Carolina Power & Light Company Department of Environmental, P. 0. Box 1551 Health and Natural Resources Raleigh, North Carolina 27602 Division of Radiation Protection P. 0. Box 27687 Raleigh, North Carolina 27611-7687 Mr. H. A. Cole Special Deputy Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director P. 0. Box 629 Public Staff -

NCUC Raleigh, North Carolina 27602 P. 0. Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Mr. C. R. Dietz Resident Inspector's Office Manager, Robinson Nuclear Project H. B. Robinson Steam Electric Plant Department Route 5, Box 413 H. B. Robinson Steam Electric Plant Hartsville, South Carolina 29550 P. 0. Box 790 Hartsville, South Carolina 29550 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Mr. Heyward G. Shealy, Chief 101 Marietta Street Bureau of Radiological Health Suite 2900 South Carolina Department of Health Atlanta, Georgia 30323 and Environmental Control 2600 Bull Street Mr. R. Morgan Columbia, South Carolina 29201 General Manager H. B. Robinson Steam Electric Plant P. 0. Box 790 Hartsville, South Carolina 29550 Meeting with CP&L and NRC on Licensing Process and Submittals August 24, 1990 Name Affiliation E. G. Adensam NRR/DRP Patricia Anderson NRR/DRP Bob Prunty CP&L/Nuc Lic.

Jan Kozyra CP&L/Nuc Lic. (HBR2)

John Eads CP&L/Nuc Lic. (HNP/RNP)

Tillie Hudson CP&L/Nuc Lic. (SNP)

Ron Oates CP&L/Nuc Lic. (BNP)

Bill Murray CP&L/Nuc Lic. (BNP)

Martha Card CP&L/Nuc Fuel/OSU Donna Kennedy CP&L/Nuc Lic.

Steve Callis CP&L -

Onsite Licensing BNP Leonard I. Loflin CP&L/Nuc. Lic.

NRC/CP&L MEETING TECHNICAL SPECIFICATION PAGES August 24, 1990 0830 - 1000 PURPOSE:

To establish a common understanding between the NRR Staff and the CP&L Licensing staff concerning the format, content, and processing of proposed changes to Technical Specification pages.

AGENDA:

o

Introductions

o NRC Processing of Technical Specification Changes (NRC)

Origin Requests Noticing Preferred Mechanics Amendment Process o

CP&L Submittal Process (CP&L)

CP&L Submittal Mechanics CP&L Maintenance of Record Copy of Technical Specifications CP&L Amendment Distribution Process o

Open Discusssion (CP&L and NRC)

License Amendment Process o Origin o Requests o Noticing (Sholly) Sequence o Preferred Mechanics

• 08 0

Origin o Orders o Requests License Technical Specifications

Requests o Submittal o Acceptance Review o Noticing o Technical Review o Amendment Package Preparation o Legal Review o Issuance

Noticing (Sholly) Sequence o Process o Acceptance Review o Publication of Notice

Preferred Mechanics o Marked-up and Original Pages o No Significant Hazards Consideration o Nomenclature

AMENDMENT PROCESS REQUEST NO SIGNIFICANT HAZARDS CONSIDERATION REVIEW TIME FOR 30 DAY NOTICE PUBLISH 30 DAY NOTICE (NSHC)

IN FEDERAL REGISTER HEARING REQUEST ??

CONSULT WITH THE STATE ISSUE AMENDMENT NOTICE IN FEDERAL REGISTER

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NO SIGNIFICANT HAZARDS CONSIDERATION Change One Basis

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Involve a significant reduction in a margin..ot safety.

Change Two Basis

1.

2.

3.

Change Three Basis

1.

2.

3.

EXAMPLES 10 CFR Part 50 10 CFR 50.36 Loss-of-Coolant Accident (LOCA)

Brunswick Steam Electric Plant, Units 1 and 2 Shearon Harris Nuclear Power Plant, Unit 1 H. B. Robinson Steam Electric Plant, Unit No. 2 Pages through have been deleted (Next page is

DEFINITIONS CHANNEL FUNCTIONAL TEST (Continued)

b.

Sistable channels -

the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

CORE ALTERATION CORE ALTERATION shall be the addition, removal, relocation, or movement of fuel, sources, incore instruments, or reactivity controls in the reactor core with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe, conservative location.

CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specifications 6.9.3.1, 6.9.3.2, 6.9.3.3, and 6.9.3.4. Plant operation within these core operating limits is addressed in individual specifications.

CRITICAL POWER RATIO The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in an assembly which is calculated, by application of an NRC approved CPR correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be concentration of 1-131, uCi/gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, r-132, 1-133, 1-134, and r-135 actually present.

The following is defined equivalent to 1 uCi of 1-131 as determined from Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites":

1-132, 28 uCi; 1-133, 3.7 uCi; 1-134, 59 uCi; I-135, 12 4Ci.

E -AVERAGE DISINTEGRATION ENERGY i shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gama energies per disintegration (in MeV) for isotopes with half lives greater than 15 minutes making up at least 95% of the total non-iodine activity in the coolant.

BRUNSWICK -

UNIT 1 1-2 Amendment No.

REACTIVrTY CONTROL SYSTEMS ROD SEQUENCE CONTROL SYSTEM L.IMITINC CONDITION FOR OPERATION 3.1.4.2 (DELETED)

SURVEILLANCE REQUIREMENTS 4.1.4.2 (DELETED)

BRUNSWICK UNIT 1 3/4 1-15 Amendment No.

DISTRIBUTION FOR MEETING

SUMMARY

DATED: December 6, 1990 Facility:

Carolina Power & Light Co.

cD o ke

'Fi-e NRC PDR Local PDR T. Murley 12-G-18 F. Miraglia 12-G-18 E. Adensam 14-B-20 P. Anderson 14-B-20 N. Le 14-B-20 R. Lo R. Becker OGC 15-B-18 E. Jordan MNBB-3302 ACRS (10)

P-315 K. Clark RH

• Copies sent persons on facility service list PI~O1