ML20217C634

Proposed Tech Specs Re Editorial Changes to Improved TS Saftey Limits & Administrative Controls to Replace Titles of Senior Vice President,Nuclear Operations & Vice President, Nuclear Production W/Position of Chief Nuclear Officer

ML20217C634
Person / Time
Site:	Crystal River
Issue date:	03/20/1998
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20217C592	List: 3F0398-17, Rev 0 to LAR 231 to License DPR-72,proposing Editoral Changes to Improved Tech Specs Safety Limits & Administrative Controls to Replace Listed Titles W/Position of Chief Nuclear Officer ML20217C634
References
NUDOCS 9803270092
Download: ML20217C634 (8)

Text

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACHMENT C LICENSE AMENDMENT REQUEST #231 REVISION 0 REDLINE / STRIKEOUT ITS & BASES PAGES Shadow / Strikeout Changes Text being added Indicated by shadowed'texi Text being deleted Indicated-by-strikeout-text

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SLs 2.0

'.2.0 SLs 2.2. SL Violations (continued)-

2.2.3 In MODES 3, 4,'and 5, if SL 2.1.2 is violated, restore compliance within 5 minutes.

2.2.4 With any SL violation, within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.5 With arty SL violation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the S: i r Yi::

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i.lli..A...agege$fjandtheoffsitereviewersspecDiedTEthe t

6r ssurance Plan.

2.2.6 With any SL violation, within 30 days, a Licensee Event' Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the offsite reviewers specified in the Quality Assurance Plan, the Director, Nuclear Plant Operations and th: ::icr Yice Prc:id::t, t:1::r 0;;r:ti:::. [ggji([@jij

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2.2.7 With any SL violation, operation of the plant shall'not be resumed until authorized by the NRC.

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g Crystal. River Unit.3 2.0-2 P.:;i:icn II JY V

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1 RCS Pressure SL B 2.1.2

", BASES,

~ SAFETY LIMIT 2.2.6

' VIOLATIONS (continued)

If the RCS pressure SL is violated, a Licensee Event Report shall be prepared and submitted within 30 days to the NRC in accordance with 10 CFR 50.73 (Ref. 9). A copy of the report shall also be provided to the NGRC, the Director, Nuclear Plant Operation, and the 5::icr Vic: Prc:id::t, "::1::r Op:r:ti:::. M{1.s.i. gjl sp10fj { R !

f The 10 CFR 50.73 part'against which;a Safety Limit violation required by Technical

1) completion of a plant. shutdown would be reported is:

Specifications,'(10CFR. 50.73(a)(2)(1)(A)),'2) an' event which resulted in an unanalyzed condition that significantly compromised plant safety. (10 CFR 50.73(a)(2)(iv)).

2.2.7 If the RCS pressure SL is violated, operation of the plant shall not be resumed until authorized by the NRC. This requirement ensures the NRC that all necessary reviews, analyses, and actions are completed by establishing limitations on ascending MODES or other specified conditions in the Applicability until the NRC review is complete.

REFERENCES 1.

FSAR, Section 1.4.

2.

ASME Boiler and Pressure Vessel Code,Section III, Article NB-7000.

3.

ASME Boiler and Pressure Vessel Code,Section XI, Articles IWA-5000 and IWB-5000.

4.

BAW-10043, May 1972.

5.

FSAR, Section 14.

6.

ASME USAS B31.7, Code for Pressure Piping, Nuclear Power Piping, February 1968 Draft Edition.

(continued)

Crystal River Unit 3 8 2.0-11 P.:;i:icn 11

(

4 OrganizatiCn

-5.2 5.0 ' ADMINISTRATIVE CONTROLS -

5.2 Organization 5.2.1' Onsite and Offsite Oraanizations Onsite and offsite organizations shall'be established for u. nit operation and corporate management, respectively. The onsite and-offsite organizations shall include the positions responsible for activities affecting safety of the nuclear power plant. '

a.

Lines of authority, responsibility, and communications shall-be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department

-responsibilities and relationships,'and job descriptions for key personnel positions, or in equivalent forms of documentation. These shall be documented in the FSAR;

"::'::yp g:jiytjg : diiEffiliiijsIj b.

The Q "ij:fr:3jd:-t pfft@bFiki'4Whie:bffWrj$^~oYeffi1~iliht'smul~ihall havehiselear bDthbrcoinpi hsti E6Ep Fiij6his~i6{llty'fo and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing,@ technical support to the plant to ensure nuclear safety; p c.

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dc. The individuals who train the operating staff, carry out health physics or perform quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

- 5.2.2 Unit Staff The unit staff organization shall include the following:

a.

One auxiliary nuclear operator shall be assigned to the operating shift any time there is fuel in the reactor and (continued)

. Crystal River, Unit'3 5.0-2; Amendment No. 449 5

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 1

DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACHMENT D LICENSE AMENDMENT REQUEST #231 REVISION 0 TECHNICAL SPECIFICATIONS & BASES Revision Bar Pages

SLs 2.0 2.0, SLs 2.2 SL Violations (continued) 2.2.3 In MODES 3, 4, and 5, if SL 2.1.2 is violated, restore compliance within 5 minutes.

2.2.4 With any SL violation, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.5 With any SL violation, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the appropriate Nuclear Operations senior management and the offsite reviewers specified in the Quality Assurance Plan.

2.2.6 With any SL violation, within 30 days, a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the offsite reviewers specified in the Quality Assurance Plan, the Director, Nuclear Plant Operations and the Chief Nuclear Officer.

l 2.2.7 With any SL violation, operation of the plant shall not be resumed until authorized by the NRC.

Crystal River Unit 3 2.0-2 Amendment No.

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V 9

RCS Pressure SL 8 2.1.2

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BASES, SAFETY LIMIT 2.2.6

' VIOLATIONS (continued)'

If the RCS pressure SL is violated, a Licensee Event Report shall be prepared and submitted within 30 days to the NRC in accordance with 10 CFR 50.73 (Ref. 9). A copy of the report-shall also be provided to the NGRC, the Director, Nuclear.

Plant Operations, and the Chief Nuclear Officer.

l

~ The 10 CFR 50.73 part against which a Safety Limit violation would be reported is:

1) completion of a plant shutdown-required by Technical Specifications, (10 CFR 50.73(a)(2)(1)(A)), 2) an event which resulted in an unanalyzed condition that significantly compromised plant safety, (10 CFR 50.73(a)(2)(iv)).

2.2.7 If.the RCS pressure SL is violated, operation of the plant

- shall not be resumed until authorized by the NRC. This requirement ensures the NRC that all necessary reviews, analyses, and actions are completed by establishing limitations on ascending MODES or other specified conditions in the Applicability until the NRC review is complete.

e REFERENCES 1.

FSAR, Section 1.4.

2.

ASME Boiler and Pressure Vessel Code,Section III, Article NS-7000.

3.

ASME Boiler and Pressure Vessel Code,Section XI, Articles IWA-5000 and IWB-5000.

4.

BAW-10043, May 1972.

s 5.

FSAR, Section 14.

6.

ASME USAS B31.7, Code for Pressure Piping, Nuclear Power Piping, February 1968 Draft Edition.

(continued)

Crystal: River Unit 3 B 2.0-11 Amendment No.

a

~

Organization 5.2

.4 5.0 ' ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1' Onsite and Offsite Oraanizations Onsite and'offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions responsible for activities affecting safety of the nuclear power plant.

a.

Lines of authority, responsibility, and communications shall be established-and defined from the highest management-levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These shall be documented in the FSAR; b.

The Chief Nuclear Officer shall be an officer of the company and shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and c.

The individuals who train the operating staff, carry out health physics or perform quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a.

One auxiliary nuclear operator shall be assigned to the operating shift any time there is fuel in the reactor and L

(continued)

Crystal River Unit 3'-

5.0-2

~ Amendment No.

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