ML20040H303

Amend 46 to License DPR-66,revising App a & B Tech Specs to Reflect Establishment of Nuclear Div within Util

ML20040H303
Person / Time
Site:	Beaver Valley
Issue date:	01/27/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20040H293	List: ML20040H292 ML20040H303 ML20040H310 ML20040H314
References
NUDOCS 8202180058
Download: ML20040H303 (16)

Text

{{#Wiki_filter:* r p* *%q k UNITED STATES + 8 NUCLEAR REGULATORY COMMISSION g WASHINGTON, D. C. 20555 5'

j

%...../ DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 l License No. DPR-66 1. The Nuclear Regulatory Commission (the Commission) has sound that: A. The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated April 10, 1981 and supplemented June 30, August 13, September 17 and December 22, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulitions; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements ' have been satisfied. 8202100058 820127 PDR ADOCK 05000334 P PDR

l e l 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License ~ No. DPR-66 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are 4 hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of its issuance. OR THE NUCLEAR REGULATORY COPHISSION \\ ) kkh g Ch e ' Operating Reactor B anch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: January 27, 1982 i i i i l l t

1 ) ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 46 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows: Remove Pages Insert Pages 6-2 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-10 6-10 6-il 6-11 6-12 6-12 Revise Appendix B as follows: Remove Pages Insert Pages 5-1 5-1 5-2 5-2 5-3 5-3 5-4 5-4

r x i ~} 5 e w w l

2:5

W Iggs g -{j 0

= l w=E l 83

=

l I egsa

• a e

="

l 2 5 35 ~1 a 55 f C m = 5. o gt" y

== w -a u 8 le~si g a. k-33 a i:! I a-)). W e w ~ *5 7

• 8 g 3 3

5'C B = 2 $2 .g.ja 1 , u = 3%E ,5 a53 c 5 3 I mI30 5 EE 555 clas O. EWS EdEj U I ~{a 333 u z e-R n. a

c. =

l g *C w g 2 M -vm 32. ie $3 !gE 5! m e 38 JO g35 lEl . ll =* E$ I!: "s" W E.

== e_

e. -

I z-1 s., ao go u

8. 5 85EW

= o,5 0 E38 s he wse s i)g W5 2 13::

s 25

u I=- I== az533 s-m5

I"

!H = ac = se

==- -wm Sat -w in ili aI u ggi E s v.s 3- =s- -1~ g-! -u si Y 5-3i ~ g*! )3 I n 8 8 g 21: I a=_ _. J 35-5 =I 1. BEAVIR VAI.LIY - UNIT 1 6-2 Amendment No. 46 l l - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _. _ ~ _ _

p 15: 32 it: -j. En "i 3:s in 8

• 1 at

!g j

3~

l

{- a 8-

• 3, u

] c-T T I j: .!3" li. Hj! 5! Es !'!l_ T ll ~ i 5 it. =1i ill 3: t l 3 l. i. 2 1-- i v. v. y v. i Hi l,ii 11 iii !i g. i i-g- 8 s i i I I i ]ij i e

jsj-

!!i-i s li i i l il 3 i -s i r.. g i I i i 3: g x i si

== 1. !:[- I. e i -=

== i -se-it

1 s1

-1

3

.= i si is ja s ~ I-5 !~ iE s

1 2-i it l

< 4 i d l e g ~! EE l I

1

!!.1 11 .la l

c i

I i y; l-o i i sif u. l 1: fi" i II !I i1. g v. !.ii !!]i l vf. Tl!_ lli .!!i i li t-1- j 11-t; Il- = 511 _1 _j -u 1 l r- .g. sil. li ii l I i .v.- ll

I liii

-iil l s i l-I- 1. _L- -r -a-l1 i l 11 i vg. .g. !.li l lg.i ill ill l 11=t-li 11ll i I-i i i I A ss8 li !!I Ib i kl kIl llo I 3] tj {8 f li III ill il 10 ii! 11 il I l lii l 3 63 BEAVER VALLEY. UNI T1 Amendment No.'46 i

ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. except for the Radiological Operations Coordinator who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shif t Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents. 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Director Nuclear Division Training l and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A' Training program for the Emergency Squad shall be maintained under the direction of the Director Nuclear Division Training and shall meet or exceed l the requirements of Section 27 of the NEPA Code-1976. 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) FUNCTION 6.5.1.1 The OSC shall function to advise the Station Superintendent on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The OSC shall be composed of the: Chairman: Chief Engineer Member: Senior Licensed Operator Member: Radiation Control Foreman Member: Maintenance Engineer j Member: Senior Engineer - Station Engineering Member: Senior Testing or Study Proj ec ts Coordinator Member: Shift Technical Advisor i Member: Chemist i NOTE: The chairman of the OSC shall appoint an individual from each of i the above listed job categories to serve as a member of the OSC i for a period of at least 6 months. 1 NOTE: OSC members shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The SRO shall meet the qualifications of Section 4.2.2 and the Maintenance Engineer will Meet the qualifications of Section 4.2.3. BEAVER VALLEY - UNIT 1 6-5 Amendment No. 46 l w 3 w y r

~- gos [ t[ ,s ALMINISTRATIVE CONTROLS f \\ ALTERNATES 6'.5.1.3 All alternate members shall be appointed in writing by the OSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSC activities at any one time. MEETING FREQUENCY 6.5.1.4 The OSC shall meet at least once per calendar =enth and as convened by the OSC Chairman or his designated alternata. QUORUM 6.5.1.5 A quorum of the OSC shall consist of the Chairman or his designated alcernate and four members including alternates. RESPONSIBILITIES 6.5.1.6 The OSC shall be responsible for: Review of 1) all procedures required by Specification 6.8 and a. changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect i nuclear safety, b. Review of all propcsed tests and experiments that affect nuclear safety, c. Review of all proposed changes to Appendix "A" Technical Specifications. d. Review of all proposed change's or modifications to plant systems or equipment that affect nuclear safety. Investigation of all violations of the Technical Specifications Y e. including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the Offsite \\ j[ Review Committee. f. Review of those REPORTABLE OCCURRENCES requiring 24 hour notification to the Commission. g. Review of facility operations to detect potential safety hazards. l l h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee. i ( l BEAVER VALLEY - UNIT 1 6-6 Amendment No. 46 ( s m -n--

r ADMINISTRATIVE CONTROLS 1. Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Chaiman of the Offsite Review Comittee. s j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Chairman of the Offsite Review Comittee. .x \\s AUTHORITY 6.5.1.7 'The OSC Shall: w a. Ra'comend to the Plant Superintendent written approval or disapproval of ' items considered under 6.5.1.6(a) through (d) above. 8 b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constit'utes an unreviewed safety question. Provide wr'itten notification within 24 hours to the Manager of c. Nuclear Ooerations and the Offsite Review Comittee of disagreement between the 0SC and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such 1 disagreements pursuant to 6.1.1 above. 'l RECORDS 6.5.1.8 The OSC shall maint!ain written minutes of each meeting and copies shall be provided to the Manager of Nuclear Operations and Chairman of the l Offsite Review Comittee. 6.5.2 0FF5ITE REVIEW COMMITTEE (ORC) FUNCTION 6.5.2.1 The ORC shall function to provide independent review and audit of designated activities in the areas of: a. nuclear power plant operations b. nuclear engineering l l A g BEAVER VALLEY - UNIT 1 6-7 Amendment No. 46 h' Ti' x $ IA

t ADMINISTRATIVE CONTROLS c. chemistry and radiochemistry d. metallurgy e, instrumentation and contrcl f. radiological' safety g. mechanical and electrical engineering h. quality assurance practices COMPOSITION 6.5.2.2 The ORC shall be composed of the: Chairman: Manager, Nuclear Safety and Licensing Vice Chairman: Managerrof Nuclear Engineering, Nuclear Division Member: Nuclear Engineer, Mechanical Engineering Department Member: Manager of Nuclear Operations Member: Instrument Engineer, Power Stations Department Member: Supervisor, Central Chemical Laboratory Pcwer Stations Department Member: Mechanical Engineer, Mechanical Engineering Department Member: Quality Assurance Manager, Quality Assurance Department Member: Coordinator, Safety Review Committee. Nuclear Division Member: Director, Environmental and Radiological Safety Programs Member: Beaver Valley Power Station Project Manager ALTERNATES ^ 6.5.2.3 All alternate menters shall be appointed in writing by the ORC Chairnen to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC. BEAVER VALLEY - UNIT 1 6-8 Amendment No. 46 l L l

AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the ORC. These audits shall encompass: I a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performance, training and qualifications of the entire l facility staff at least once per 12 months. c. The results of actions taken to correct deficiencias occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months. d. The performance of activities required by the Quality Assurance i Program to meet the criteria of Appendix "B," 10 CFR 50, at least l cnce per 24 months. e. The Facility Emergency Plan and implementing procedures at least j once per 24 months. f. The Facility Security plan and implementing procedures at least once per 24 months. 6 g. Any other area of facility operation considered appropriate by the ORC or the Vice President, Nuclear. h. The Facility Fire Protection Program and implementing procedures at least once per 24 months. 1. An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 1 months utili:ing either qualified offsite licensee personnel or an outside fire protection firm. j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outsider fire consultant at least once per 36 months, AUTHORITY 6.5.2.9 The ORC shall report to the Manager of Nuclear Safety and Licensing and advise the Vice President, Nuclear Division *cn those areas of responsi-bility specified in Sections 6.5.2.7 and 6.5.2.8. RECOROS 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated on the following pages: BEAVER VALLEY - UNIT 1 6-10 Amendment No. 46 r v

ADMINISTRATIVE CONTROLS 4 a. Minutes of each ORC meeting shall be prepared, approved and fomarded to the Vice President, Nuclear Division within 14 days following each meeting. b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and fomarded to the Vice President, Nuclear Division within 14 days following completion of the review. c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Nuclear Division and to the l management positions responsible for the areas audited within 30 days after completion of the audit. d. The chairman of the ORC shall review all recomendations of the ORC and shall forward such recomendations to the Vice President, Nuclear Division. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPCRTABLE OCCURRENCES: a. The Comission shs!1 be notified and/or a report submitted pursuant to the requiraments of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewed by the OSC and submitted to the ORC and the Manager of Nuclear Operations. l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The facility shall be placed.in at least HOT STANDBY within I hour, b. The Safety Limit violation shall be reported to the Comission, the Manager of Nuclear Operations and to the ORC within 24 hours, c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the OSC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility component:, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Comission, the ORC and the Manager of Nuclear Operations i within 10 days of the violation. I I l BEAVER VALLEY - UNIT 1 6-11 Amendment No. 46 i

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES l 6.8.1 Written procedures shall be established, implemented and maintained covering the activitiws referenced below: a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972. b. Refueling operations. c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program implementation. 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the OSC and approved by the Plant Superintendent, predesignated alternate or a predesignated Department Manager to whom the Plant Superintendent has assigned in writing the responsibility for review and approval of specific subjects considered by the committee, as applicable. 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: i a. The intent of the original procedure is not altered. b. The change is approved by two members of the plant managcment staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. 'The change is documented, reviewed by ths OSC and approved by the c. i Plant Superintendent within 14 days of implementation. 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted. l l t l l BEAVER VALLEY - UNIT 1 6-12 Amendment No. 45 l

5.0 ADMINISTRATIVE CONTROLS Objective i To define the organization, assign responsibilities, describe the i environmental surveillance procedures, provide for a review and audit 1 function and prescribe the reporting requirements in order to insure continuing protection of the environment and implement the Environmental Technical Specifications. I 5.1 ORGANIZATION Figure 5.1-1 is a partial organization chart of the Nuclear Division l which includes groups and individuals responsible for environmental protection, environmental monitoring and the implementation oi the Environmental Technical Specifications following the issuance of an operating license for Beaver Valley Unic No. 1. 5.2 RESPONSIBILITY All activities within the Nuclear Division are the responsibility of the Vice President, Nuclear. He delegates the responsiblity for the radiological and ecological environmental monitoring programs to the Manager, Nuclear Safety and Licensing. He is advised by the l Off-Site Review Committee in matters relating to the environmental impact of station operation which involve proposed changes to the i Environmental Technical Specifications, proposed changes to written procedures, proposed changes or modifications to station systems or equipment, evaluations of investigations, and when appropriate, i recommendations to prevent recurrence of such violations. The Station Superintendent is the individual charged with the respon-sibility for assurin5 that all releases to the environment shall be limited in accordance with the Limiting Conditions for Operations as described in the Environmental Technical Specifications. Controlled releases are made utilizing written procedures undel the direction of the Shift Supervisor at the request of the Reactor Control Chemist who specifies the release rate, the station operating conditions, and the monitoring requirements which must be maintained during the release to comply with the technical specifications. These activities are reviewed by the Results Coordinator and the Station Operating Supervisor and audited periodically under the direction of the Manager of Nuclear Safety and Licensing. The Station Superintendent is also responsible for the issuance of the 24-hour reporting requirement to the Director of Regional Regulatory Operations Office, when required. BEAVER VALLEY UNIT 1 5-1 Amendment No. 46

cn9g Vice Prealdent so Nuclear Division f I E Manager Manager [ E Nuclear Operations Nuclear Safety Q and I.icensing l ORC Station coordination Director Superinteaulent --- - - -- -+- - - - - -- Environmental and Radiological Safety Programs I I *VI'W E Station I Staff Y Environmental Coordinator-On-Situ l Environmental Program Off-Situ (Effluents) Environmental k Programs E 2 a Figure 5.1-1 2 Dusguesne Light Company o Nuclear Division ,m Partial Organization Chart Relative to Environmental Matters m

5.3 REVIEW AND AUDIT _ The Director, Environmental and Radiological Safety Programs is l responsible to the Off-Site Review Committee for reviewing the results ( of the Environmental Surveillance Program to determine that the sampling program is being implemented as described to verify that the environment is adequately protected under the existing station operating procedures. He is also responsible for requesting that analyses be repeated or that new samples be obtained from particular locations in the case of anomalous results. The Director, Environmental and Radiological Safety Programs is respon-l sible to the Off-Site Review Committee for scheduling audits utilizing various company personnel to verify that station operations including releases to the environment are conducted in such a manner that contin-uing protection to the environment is provided. The Director, Environ-mental and Radiological Safety Programs shall also have the responsibility for reviewing off-site environmental program sampling, analyses and calibration procedures as sunusarized in Table 3.1-3 and 3.2-1 and described in Sections 3.0 and 5.5.1 of these specifications. The Beaver Valley Power Station Superintendent is responsible for approving on-site procedures relative to the environent as described in Tables 2.4-2 and 2.4-4 and described in Sect!on 2.0 and Section 5.5.1 of these specificationr. The Off-Site Review Committee functions as they relate to the Environ-mental Technical Specifications are as follows: a. Review the reports of the Director, Environmental and Radio-logical Safety Programs on the results of the environmental monitoring program prior to their submittal to the NRC in each Annual Environmental Operating Report. See Section 5.6.1. b. Review and maka recommdadations on proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes. Review proposed changes or modifications to plant systems c. i or equipment and the evaluated impact which would require a change in the procedures described in (d) below. t d. Raview reported instances of violations of Environmental Technical Specifications and abnormal environmental occur-rences. Where investigation indicates, evaluate and for-I mulate recommendations to prevent recurrences. l T Schedule audits of station operation with regard to the e. control of releases to the environment.' I f. Review and compara the Safety Technical Specifications and ( g the Environmental Technical Specifications to avoid conflicts and maintain consistency. l-l BEAVER VALLEY UNIT 1 5-3 Amendnent No. 46 1 g r ~ _.

5.4 ACTION TO BE TAKEN IF A LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Remedial Action Immediate remedial actions as permitted by these technical specifications will be implemented until such time as the limiting condition for operation is met. 5.4.2 Investigation The Manager, Nuclear Safety and Licensing shall direct that an l investigation be conducted to determine the cause of the occurrence and recommand both temporary and permanent corrective action to prevent a recurrence. The results of this investigation shall be reviewed and approved by the Off-Site Review Committee and the Manager, Nuclear Operations. l 5.4.3 Report The occurrence shall be reported to the NRC as specified in Section 5.6.2. a 5.5 PROCEDURES 5.5.1 Written Precedures Detailed written proco+tres, including check lists and special instructions when requirad, will be prepared and implemented for all activities involving releases to the environment, described in Sections 2.0 and 3.0, the sampling and monitoring of these releases and the conduct of the Environmental Surveillance Program. These procedures will include sampling, instrument calibration, analysis, and actions to be taken when linics are approached or exceeded. Testing and calibration frequencies of effluent alarms and monitoring instruments will be included. These frequencies wf.ll be decemined from experience with similar instruments in similar environments and from manufacturers' recommendations. 5.5.2 Standard operating Procedures Plant standard operating procedures will include, when. required, sufficient precaution, limitations, and setpoints to ensure that all plant systems and components are operated in compliance with the limiting conditions for operations established in Section 2.0 of these techaical specifications. 5.5.3 Reviews All procedures described above, and all changes thereto, will be reviewed prior to implementation and periodically thereafter as described in Section 5.3. Temporary changes to procedures which do not change the intent of the original procedure may be made without the need for review by NRC. Changes to procedures for programs in Section 3 will be reviewed by the NRC. Such changes will be documented. ] BEAVER VALLEY, UNIT 1 5-4 knendment No. 46 i}}